[email protected] mayak” pa · 2017-12-20 · (automatic smoke detectors in fire alarm...

[email protected] 3FSUE “Mayak” PA

FSUE “Mayak” PA www.po-mayak.ru [email protected]


Federal State Unitary Enterprise «Mayak» Production Association is the first Russian nuclear industrial site. Present-day PA «Mayak» is an up-to-date and dynamically developing enterprise of the State Atomic Energy Corporation «Rosatom».

«Mayak» PA is the leading Russian and one of the biggest world manufacturers of sealed radionuclide sources.

The product mix offered today by «Mayak» PA to domestic and foreign customers, includes more than 200 codes of alpha-, beta-, gamma- and neutron sources with various dimensional and radiation specifications, and with reactor isotopes Cobalt-60, Iridium-192, fission isotopes Caesium-137, Americium-241, Plutonium-239, Promethium-147, Strontium-90, etc., as their active material, as well as bulk isotopes with Carbon-14 and Helium-3 gas among them.

Ionising sources are widely used for various scientific and technical applications such as radiation processing equipment, oil-well logging, industrial NDT instruments, gamma-radiography, various process control and measurement instruments and other gauges, and also in medicine.

At present, acting under the Federal Law dated 11.07.2011, No. 190-FZ, «Mayak» PA accepts for long-term storage and re-processing the disused ionising sources operated in Russia and made both by «Mayak» PA and other manufacturers and Mayak’s origin sources operated outside Russia.

At present «Mayak» PA has become an independent player in the market of re-sourcing of radiation facilities and machines. «Mayak» PA offers «from cradle to grave» service package that covers the entire life-cycle of the sources from their manufacture to disposal and allows working directly with organisations operating Mayak’s origin sources. Shorter lead time and lower cost of re-sourcing are the obvious benefits for the potential customers.

«Mayak» Production Association have all the resources required to develop and manufacture ionising sources, both of its own design and custom made, and render services: in-house raw material production capacities for internal manufacture of reactor and fission isotopes, dedicated production and testing facilities, highly qualified and skilled personnel, reliable process engineers.


FEDERAL STATE UNITARY ENTERPRISE «MAYAK» PRODUCTION ASSOCIATION

OF THESTATE ATOMIC ENERGY CORPORATION «ROSATOM»

Address:31 Lenin St., OzyorskChelyabinsk Region

456780

www.po-mayak.ru

CONTACTING DETAILS:

Delivery of isotope products, service package for re-sourcing radiation equipment and disposal of disused sourcesPlanning and Sales Department of Radioisotope PlantTel.: +7 (35130) 3 55 95, 3 55 09Tel./Fax: +7 (35130) 3 55 56, 3 55 57e-mail: [email protected] [email protected]

Marketing DepartmentTel.: +7 (35130) 3 34 25Tel./Fax: +7 (35130) 3 38 26e-mail: [email protected]

Technical IssuesProduction and Technical Department of Radioisotope Plant Tel.: +7 (35130) 3 56 19 (1009)Tel./Fax: +7 (35130) 3 55 56, 3 55 57e-mail: [email protected] [email protected]

Re-sourcing of gamma-therapy units, R&D on medical isotopes, radiopharmaceuticalsTel.: +7 (35130) 3 55 05, 3 55 95Tel./Fax: +7 (35130) 3 55 56, 3 55 57e-mail: [email protected] [email protected] [email protected]

Transportation, logisticsLogistics manager of Planning and Sales Department of Radioisotope PlantTel.: +7 (35130) 3 57 19Tel./Fax: +7 (35130) 3 55 56, 3 55 57e-mail: [email protected] [email protected] [email protected]


ALPHA-SOURCES3 Pu239: AIP-MIR-3А, AIP-RIG

4 Pu239: ADI, AIP-RID, AIP-EDGH

5 Pu239, U234, U238: 1 – 6P9, 1 – 6U4, 1-6U8

7 Pu239: AIP-N

8 Pu239: T-5, T-6, T-14 – T-16

ALPHA- AND BETA-SOURCES9 Pu239and Sr90+Y90: T-11, T-12

BETA-SOURCES10 Pm147: BIP-10 – BIP-50, BIP-R1, BIP-R2, BIP-K1,

BIP-K2, BIP-7, BIP-M, BIP 50x150

12 Pm147: BIP-N-1, BIP-N-2

13 Sr90+Y90: BIS-R, BIS-K, BIS-6A, BIS-F

15 Sr90+Y90: 1 – 6S0

16 Sr90+Y90: BIS-10 – BIS-50

17 Sr90+Y90: BIS-MNA, BIS-MNB

18 Sr90+Y90: BIS-4AN

19 Sr90+Y90: BIS-1, BIS-2, BIS-MN-2, BIS-M-LA, BIS-MN-4

20 Sr90+Y90: T-1 – T-4, T-17 – T-20, T-22, T-13, T-21

GAMMA-SOURCES21 Ir192: GIID-1 – GIID-11a-4

23 Ir192: GIID-12-0.5 – GIID-15-4

25 Cs137: IGI-C-3-1 – IGI-C-22-1

27 Cs137: M37C02-01 – M37C24-44

32 Cs137: IGI-C-36 – IGI-C-42

34 Cs137: GID-C, IMGIC

36 Co60: K-3, K-3A

37 Co60: GIT-K

38 Co60: GIK

41 Co60: GIK-A6, GIK-A6m

42 Co60: M2089

43 Co60: GSOO.061

44 Am241: IGIA

NEUTRON SOURCES 46 Pu239: IBN-1 – IBN-28

48 Pu238: IBN-8-1 – IBN-8-9

49 Am241: IBN-241

53 Am241: M41H72-45 – M41H72-71

X-RAY SOURCES54 Pu238: IRIPL series

55 Fe55: IRIZh series

56 Sr90+Y90: IRIS series

57 Pm147: IRIP series

58 Tl204: IRIT series

BULK ISOTOPES59 Americium-241 dioxide

60 Plutonium-238 dioxide

61 Helium-3

62 Krypton-85

63 Carbon-14

64 Strontium-90 Carbonate

Tel./Fax: (35130)-35556,(35130)-35557www.po-mayak.rue-mail: [email protected]\

CONTENTS


2. AIP-RIG Source1. AIP-MIR-3А Source

12Х18Н10T steel 12Х18Н10T steel

08 kp steel

D

d

H

Dd

working window

working window

H

Notes:Integrity Rating according to the State Standard GOST R 52241(ISO 2919) is “ISO/99/С34141” for AIP-MIR-3А sources and “ISO/99/С34141” for AIP-RIG sources.The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by a wet wipe test; pass limit – 37 Bq when tested at the manufacturer’s site, 74 Bq during the designated working life, transportation and storage.

Principal Technical SpecificationsThe sources comprise a body, a lid (hold-down annular retainer), and an enamelled insert incorporating plutonium isotopes activity deposit and mounted between the body and the lid. Body-lid (annular retainer) joint in the sources is welded by spot welding.The designated working life is 10 years from the date of QC final acceptance.

ApplicationRadioisotope instruments (automatic smoke detectors in fire alarm systems, gas chromatographers, gas analyzers, etc.).

AIP-MIR-3А, AIP RIG Sources

Source Code

Dimensions of the Source (Working Window),

mmEnergy Flux of

External Alpha-Emission,

W

Maximum Content Activity of Plutonium Isotopes in a

Source

Diameter,D (d)

Height,H Bq Ci

1 AIP-MIR-3А 41 (37) 3.5 (3.20 ± 1.30)∙10-6 5.90∙107 1.60∙10-3

2 AIP RIG 22 (17) 30 (2.00 ± 0.40)∙10-6 4.10∙107 1.10∙10-3

Pu239 alpha-emission

08 kp steel


3. AIP-EDGH Source

2. AIP-RID Source1. ADI Source

Aluminium alloy

ceramic

Aluminium alloy

ceramic

ceramic

D D

Dd

H

working surface

working surface

working surface

H

H

Notes:Integrity Rating of the sources is “ISO/99/С34141” according to the State Standard GOST R 52241 (ISO 2919).The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by:– wet wipe test for AIP EDGH; pass limit – 185 Bq;– dry wipe test for ADI and AIP-RID; pass limit - 18.5 Bq.* AIP-RID and AIP-EDGH are designed without a set screw.

Principal Technical SpecificationsThe sources comprise a body, and an insert designed as a ceramic sleeve with plutonium isotopes activity deposit that acts as an active component. Design of the ADI sources incorporates a set screw for alpha-emission adjustment.* The active sleeve is glued to the body in ADI and AIP-RID designs. The designated working life is 10 years from the date of QC final acceptance.

ApplicationRadioisotope instruments (automatic smoke detectors in fire alarm systems, gas chromatographers, gas analyzers, etc.).

ADI, AIP-RID, AIP-EDGH Sources

Source Code

Source Dimensions, mm Energy Flux of External

Alpha-Emission, W

Maximum Content Activity of Plutonium Isotopes in a Source

DiameterHeight,

H Bq Ciinner,d

outer,D

1 ADI 16 23.5 (4.0 – 12.0)∙10-7 2.1∙107 5.7∙10-4

2 AIP-RID 8.6 9.8 (5.6 – 12.0)∙10-9 2.1∙105 5.7∙10-6

3 AIP-EDGH 5.6 min 8.6 max 8 max (4.0 – 12.0)∙10-7 2.1∙107 5.7∙10-4



2. 6P9, 6U4, 6U8 Sources1. 1 – 5P9, 1 – 5U4, 1 – 5U8 Sources

dD

Hworking window

12Х18Н10T steel LW

lw

12Х18Н10T steel

working window

Notes:Integrity Rating of the sources is “ISO/99/С22212” according to the State Standard GOST R 52241 (ISO 2919).The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by a dry wipe test of non-working surface; pass limit:a) 1 Bq for the sources with nominal activity content in a source equal to or less than 1.00·103Bq;b) 2 Bq for the sources with nominal activity content in a source more than 1.00·103Bq.

Principal Technical SpecificationsThe sources are designed as a 1.5 mm ± 0.2 mm thick backing plate, with radioactive material deposited on its working window (in the cavity) and protected with a metal oxide film.The designated working life is 10 years from the date of QC final acceptance.

ApplicationAs radionuclide activity reference standards for calibration and graduation of radiometric instruments.

1 – 6P9 Source Series

Source Code Radionuclide

Dimensions

Nominal Content Activity of Pu239 in a

Source,Bq

Source, mm Working Window

Diameter(Length)

D (L)

Height(Width)H (W)

Diameter(length),

d (l),mm

Width,w,

mm

Surface Area,cm2

1

1Р9

Pu239

35

1.5

12

—

1 4.00 – 1.00·105

2Р9 52 22 4 1.60·101 – 4.00·105

3Р9 66 36 10 2.50·101 – 1.00·106

4Р9 101 71 40 2.50·101 – 4.00·106

5Р9 143 113 100 2.50·101 – 1.00·107

2 6Р9 (185) (135) (155) 105 160 2.50·101 – 1.60·107

Pu239, U234, U238 alpha-emission


1 – 6U4, 1 – 6U8 Source Series


Dimensions

Nominal Content Activity of U234 or U238

in a Source,Bq


Diameter(Length)

D (L)

Height(Width)H (W)

Diameter(length),

d (l),mm

Width,w,

mm

Surface Area,cm2

1

1U4

U234

35

1.5

12

—

1 4.00 – 4.00·101

2U4 52 22 4 6.3 – 1.60·102

3U4 66 36 10 1.00·101 – 2.50·102

4U4 101 71 40 2.50·101 – 4.00·102

5U4 143 113 100 4.00·101 – 6.3·102

2 6U4 (185) (135) (155) 105 160 6.3·101 – 1.00·103

1

1U8

U238

35

1.5

12

—

1 4.00

2U8 52 22 4 6.3 – 1.60·101

3U8 66 36 10 1.60·101 – 4.00·101

4U8 101 71 40 2.50·101 – 1.60·102

5U8 143 113 100 4.00·101 – 4.00·102

2 6U8 (185) (135) (155) 105 160 2.50·101 – 6.3·102



1. AIP-N Source

LW

lw

h

Notes:Integrity Rating of the sources is “ISO/99/С34141” according to the State Standard GOST R 52241 (ISO 2919).The sources are leak tested by a dry wipe test according to the State Standard GOST R 51919 (ISO 9978); pass limit – 74 Bq.

Principal Technical SpecificationsThe sources are designed as a 2.8max mm thick backing plate, with radioactive material deposited on its working window and protected with a metal oxide film. The designated working life is 10 years from the date of QC final acceptance.

ApplicationStatic eliminators.

AIP-N Sources

Source Code

Radio-nuclide


mm Energy Flux of External Alpha-Emission of the

Source, W, not less than

Exposure Dose Rate of X-ray and Gamma Emission at a Distance 0.5

m, A/kg, not more than

Maximum Content Activity

of Plutonium Isotopes in a

Source,Bq (Ci)

Length,L (l)

WidthW (w)

Height,H

AIP-N Pu239 70.95 (60) 35.8 (25) 2.8 1.0∙10-5 3.9∙10-11 3∙108 (8.1∙10-3)

08 kp steel

working window



Principal Technical SpecificationsThe sources are designed as a backing plate, with radioactive material deposited on its working window and protected with a metal oxide film. The designated working life is 2.5 years from the date of QC final acceptance.

T-5, T-6, T-14 – T-16 Sources

Notes:Integrity Rating of the sources is “ISO/99/С24242” according to the State Standard GOST R 52241 (ISO 2919).The sources are leak tested by wiping the entire surface with a dry swab; pass limit – 185 Bq.

ApplicationTo check operability of dosimetry equipment when used in sealed shutter-type detectors.

2. T-6 Sources1. T-5, T-14 – T-16 Sources


Dimensions

External Alpha-Emission,

s-1

Content Activity of Plutonium Isotopes in a Source, Bq (Ci)

diameter (length)

D (L)

Height(width),H (W)

1 Т-5

Pu239

14 0.35 (4.0 – 12.0)·102 2.9·103 (7.8·10-8)

2 Т-6 42 0.35 (6) (2.5 – 7.5)·102 1.8·103 (4.8·10-8)

1

Т-14 14 0.35 (4.0 – 12.0)·103 2.9·104 (7.8·10-7)

Т-15 14 0.35 (1.5 – 4.5)·104 1.1·105 (2.9·10-6)

Т-16 14 0.35 (1.5 – 4.5)·103 1.1·104 (2.9·10-7)



1. T-11, T-12 Sources

Notes:The sources are leak tested by wiping the entire surface with a dry swab with pass limit 185 Bq for alpha-sources and with a wet swab with pass limit 1500 Bq for beta-sources.


ApplicationTo check operability of dosimetry and radiometric equipment when used in sealed shutter-type detectors.

T-11, T-12 Sources


Source Dimensions, mm External Emission,s-1 Content Activity of

Radionuclides in a Source, Bq (Ci),not more than

Diameter (Length)

D (L)

Height(Width),

H (W)Alpha Beta

Т-11 Pu239 and Sr90+Y90

42 0.35 (6) (2.5 – 7.5)∙102 (1.0 – 3.0)∙103 8.4∙103 (2.3∙10-7)

Т-12 42 0.35 (6) (2.5 – 7.5)∙102 (5.0 – 15.0)∙102 5.1∙103 (1.4∙10-7)

Pu239и Sr90

+Y90alpha-emission, beta-emission


1. BIP-10 – BIP-50 Source Series

Dd

H12Х18Н10T steel

08 kp steel

working window

2. BIP-R1, BIP-R2 Sources


Principal Technical SpecificationsThe sources comprise a body, a lid and an enamelled insert glued into the source assembly; Promethium-147 activity is deposited on the working surface of the insert and immobilized by a protective layer of titanium dioxide or pyrolitic chromium. Body-lid joint in the sources is welded by spot welding.The designated working life is 5 years from the date of QC final acceptance.

ApplicationRadioisotope instruments, ion generators, static eliminators.

Source Code

Dimensions, mm

External Beta-Emission of the Source,

s-1

Exposure Dose Rate of X-ray and Gamma Emission at a

Distance 0.5 m from the Source

Surface(not more than),

A/kg

Maximum Content Activity

of Pm147 in a Source Diameter,

DLength,

L (l)Width,W (w)

Height,H

1

BIP-10 20 (10) – –

3

(1.25 – 20)·107 6.2·10-11 1.2·109 (3.24·10-2)

BIP-20 30 (20) – – (1.25 – 50)·107 27·10-11 2.8·109 (7.6·10-2)

BIP-30 40 (30) – – (1.25 – 63)·107 54·10-11 5.9·109 (15.9·10-2)

BIP-40 50 (40) – – (1.25 – 80)·107 77·10-11 1.1·1010 (2.97·10-1)

BIP-50 60 (50) – – (1.25 – 80)·107 77·10-11 1.1·1010 (2.97·10-1)

2BIP-R1

– 60 (56) 10 (7)

3

7.6·107 1.6·10-11 1.1·109 (2.97·10-2)

BIP-R2 3.1·107 1.2·10-10 3.0·109 (8.1·10-2)

3BIP-К1

– 63 (см.рис.3)

29 (см.рис.3)

3.6·107 1.6·10-11 4.5·108(1.22·10-2)

BIP-К2 1.7·108 3.9·10-11 1.9·109 (5.13·10-2)

4 BIP-7 12,7 (4) – – 19 1.9·107 1.6·10-11 7.4·108 (2.00·10-2)

5 BIP-М 6 (3) – – 7 7·107 1.6·10-11 3.7·108 (1.00·10-2)

6 BIP 50х150 – 160 (150) 60 (50) 5 (6.0 – 12)·108 20·10-10 5.2·1010 (1.41)

working window

H

L W

08 kp steel

wl

Pm147 beta-emission


3. BIP-K1, BIP-K2 Sources

4. BIP-7 Sources

5. BIP-M Sources

6. BIP 50x150 Sources

H

working window

08 kp steel W

Lworking window

08 kp steel

12Х18Н10T(-ID) steel

H

D

D

working window

08 kp steel

12Х18Н10T(-ID) steel H

H

12Х18Н10T(-ID) steel

08 kp steelworking window

W

L

w

d

d

w

l

l

Pm147 beta-emission


1. BIP-N-1, BIP-N-2 Sources


Principal Technical SpecificationsEnamelled steel backing plate with Promethium-147 activity deposited on the working surface of the plate and immobilized by a protective layer of titanium dioxide. The designated working life is 10 years from the date of QC final acceptance.

ApplicationRadioisotope instruments, ion generators, static eliminators.

BIP-N-1, BIP-N-2 Sources

Source Code

Dimensions of the Source (Working Window), mm

External Beta-Emission of the Source

(not less than),

s-1

Exposure Dose Rate of X-ray and Gamma Emission at

a Distance 0.5 m from the Source Surface

(not more than),

A/kg

Maximum Content Activity of Pm147 in

a Source

Bq CiLength,L (l)

Width,W (w)

Height,

H

BIP-N-1 70.95(60)

35.8 (25) 2.8

4.1·108 1.3·10-11 4.0·109 10.8·10-2

BIP-N-2 1.2·109 6.5·10-11 2.0·1010 0.54

LW

lw

h 08 kp steel

working window

Pm147 beta-emission


4. BIS-F Source

3. BIS-6A Source

2. BIS-K Source

1. BIS-R Source

Aluminium alloy

K 260v/12Х18Н10T steel

working window

H Aluminium alloy


working window

L

W

H

12Х18Н10T steel

Aluminium alloy

12Х18Н10T steel

working window

H

D

Aluminium alloy


working windowW

D

H L

Notes:Integrity Rating of the sources is C 34444 according to the State Standard GOST 25926 (ISO 2919).The sources are leak tested by immersion test according to the State Standard GOST R 51919 (ISO 9978); pass limit –200 Bq.

Principal Technical SpecificationsThe sources comprise a body, a lid and an insert with Strontium 90+Yttrium 90 activity deposited on it. The active insert is mounted between the source body and lid. The sources are sealed with glue and aluminium alloy foil.The designated working life is 3.5 years from the date of QC final acceptance.

ApplicationRadioisotope instruments

Sr90 +Y90

beta-emission


BIS-R, BIS-K, BIS-6A, BIS-F Sources

Source Code

Source Dimensions, mm

External Beta Emission of the

Source, s-1

Maximum Exposure Dose Rate of X-ray and Gamma

Emission at a Distance 0.5 m from the Source

Surface, (not more than),

A/kg

Maximum Content Activity of

Sr90+Y90 in a Source

Diameter(Length)

D (L)

Height(Width)H (W)

Bq mCi

1 BIS-R 22 10 (6.4±2.2)∙108 1.0∙10-9 6.00∙109 162

2 BIS-K (85) 4 (43) (2.80±1.00)∙108 4.7∙10-10 2.30∙109 62.0

3 BIS-6A 11 12,5 (1.10±0.50)∙108 6.7∙10-11 1.20∙109 32.0

4 BIS-F (108) 4 (54) (8.3±4.0)∙107 3.4∙10-11 7.4∙108 20.0

Sr90 +Y90

beta-emission


2. 6S0 Sources1. 1 – 5S0 Source Series

dD

Hworking window

Aluminium alloy LW

lw

Aluminium alloy

working window

Notes:Integrity Rating of the sources is “ISO/99/С22212” according to the State Standard GOST R 52241 (ISO 2919).The sources are leak tested by a wet wipe test of the entire source surface according to the State Standard GOST R 51919 (ISO 9978); pass limit – 10 Bq.The sources are supplied by the piece, in batches and as kits.* Deviation of the measured radionuclide content activity in the sources from the nominal values is not more than ±30 %.

Principal Technical SpecificationsThe sources are designed as a 1.5±0.2 mm thick backing plate, with radioactive material deposited on its working window (in the cavity) and protected with aluminium alloy foil. The designated working life is 10 years from the date of QC final acceptance.

ApplicationAs radionuclide activity reference standards for calibration and graduation of radiometric instruments.

1 – 6S0 Source Series

Source Code

Dimensions

Nominal Activity of Sr90+Y90 in a Source*,

Bq


Diameter(Length)

D (L)

Height(Width)H (W)

Diameter(Length),

d (l),mm

Width,w,

mm

Surface Area,cm2

1

1S0 35

1.5

12

—

1 1.30·101 - 3.20·106

2S0 52 22 4 2.10·101 - 1.30·107

3S0 66 36 10 8.0·101 - 3.20·107

4S0 101 71 40 2.10·102 - 1.30·108

5S0 143 113 100 8.0·101 - 2.10·108

2 6S0 (185) (135) (155) 105 160 8.0·101 - 2.10·108

Sr90 +Y90

beta-emission


1. BIS-10 – BIS-50 Source Series

12Х18Н10Т steel

08 kp/12Х18Н10Т steel

working window

Dd

H

active component

Principal Technical SpecificationsCapsule with an active component in the form of enamel matrix, zeolite granule, or glass bead, saturated with Strontium 90+Yttrium 90 radionuclides. The designated working life is 5 years from the date of QC final acceptance.

ApplicationProcess control instruments

Notes:– Integrity Rating according to the State Standard GOST R 52241 (ISO 2919) is “ISO/99/C53343” for BIS-10 and BIS-20 and “ISO/99/C33343” for the rest of the source codes of this series.– Capsules are argon-arc (TIG) seal welded.– The sources are leak tested by immersion test according to the State Standard GOST R 51919 (ISO 9978); pass limit - 200 Bq.

BIS-10 – BIS-50 Source Series

Source Code

Dimensions of the Source (Working

Window), mmNominal


Source,s-1

Exposure Dose Rate of X-Ray and Gamma Emission at a Distance 0.5 m from the Source

Surface (not more than),

A/kg

Maximum Content Activity of Sr90+Y90 in a

Source

Bq mCiDiameter,D (d)

Height,H

BIS-10 22 (10) 10 (0.8 – 200)·107 3.3·10-9 4.40·1010 1.19

BIS-20 36 (20) 15 (0.8 – 1000)·107 2.0·10-8 2.20·1011 5.9

BIS-30 46 (30) 15 (0.8 – 1000)·107 2.0·10-8 2.30·1011 6.2

BIS-40 58 (40) 16 (0.8 – 1000)·107 2.0·10-8 2.30·1011 6.2

BIS-50 70 (50) 16 (0.8 – 1000)·107 2.1·10-8 2.30·1011 6.2

Sr90 +Y90

beta-emission


2. BIS-MNB Source Series1. BIS-MNA Source Series

12Х18Н10Т steel

working window

D

Hactive component (granule)

D

H

12Х18Н10Т steel

working window

active component (granule)

Notes:Integrity Rating of the sources is “ISO/99/С55443” according to the State Standard GOST R 52241 (ISO 2919).Capsules are argon-arc (TIG) seal welded.The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by:a) vacuum bubble test; pass criterion – no bubbles observed;b) immersion test; pass limit – 200 Bq.

Principal Technical SpecificationsCapsule with an active component in the form of borosilicate-glass or zeolite granule saturated with Strontium 90+Yttrium-90 radionuclides.The designated working life of the sources is 70000 hours from the date of QC final acceptance, and 12 years (105192 hours) for BIS-MNA-1 sources assembled into TBFU 164-12.

ApplicationRadioisotope instruments intended for operation in severe temperature and vibration environment.

BIS-MNA, BIS-MNB Sources

Source Code

Dimensions of the Source, mm External Beta

Emission of the Source,

s-1

Exposure Dose Rate of X-ray and Gamma Emission at a Distance 0.5 m from the Source Working Window (not

more than),

A/kg

Maximum Content Activity of Sr90+Y90 in

a Source

Diameter,D

Height,H Bq mCi

1BIS-MNA-1 with

M6 x 0.75 thread

8.0

(4.8 – 8.0)·106 1.3·10-11 18.5·107 5

BIS-MNA-2 (1.6 – 2.3)·107 3.9·10-11 75.0·107 20.3

2BIS-MNB-1

6.0(4.8 – 8.0)·106 1.3·10-11 18.5·107 5

BIS-MNB-2 (1.6 – 2.3)·107 3.9·10-11 75.0·107 20.3

Sr90 +Y90

beta-emission


1. BIS-4AN Source

12Х18Н10Т steel

working window

D

Hactive component (granule)

Notes:Integrity Rating of the sources is “ISO/99/С54443” according to the State Standard GOST R 52241 (ISO 2919).The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by:a) vacuum bubble test; pass criterion – no bubbles observed;b) immersion test; pass limit – 200 Bq.

Principal Technical SpecificationsCapsule with an active component in the form of zeolite granule saturated with Strontium 90+Yttrium-90 radionuclides.The designated working life of the sources is 8 years from the date of QC final acceptance.

ApplicationRadioisotope instruments intended for operation in severe temperature and vibration environment.

BIS-4AN Source

Source Code

Dimensions of the Source,

mmExternal Beta

Emission of the Source,

s-1

Exposure Dose Rate of X- ray and Gamma Emission at a Distance 0.5 m from the Source Working Window (not

more than),

A/kg

Maximum Content Activity of Sr90+Y90 in a

Source

Diameter,D

Height,H Bq mCi

BIS-4AN 10.2 12.0 (2.0 – 3.2)·107 3.9·10-11 9.3·108 25.0

Sr90 +Y90

beta-emission


3. BIS-MN-4 Source

2. BIS-MN-2, BIS-M-LA Sources1. BIS-1, BIS-2 Sources

Aluminium alloy

working window

D

H


12Х18Н10Т steel

Aluminium alloy


d

d

H

D

H

D

d

12Х18Н10Т steel

working window


Notes:– Sources BIS-1 and BIS-2 are sealed with glue, BIS-MN-2, BIS-MN-4 and BIS-M-LA are argon-arc (TIG) seal welded.– Integrity Rating according to the State Standard GOST R 52241 (ISO 2919) is “ISO/99/C34443” for BIS-1, BIS-2 and “ISO/99/С55443” for BIS-MN-2, BIS-МN-4 and BIS-M-LA designs.– The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by immersion test; pass limit – 200 Bq.

Principal Technical SpecificationsCapsule with an active component in the form of enamel matrix, zeolite granule, or glass bead, saturated with Strontium-90 + Yttrium-90 radionuclides.The designated working life of the sources is 2.5 years from the date of QC final acceptance for BIS-1, BIS-2, and 5 years from the date of QC acceptance for BIS-MN-2, BIS-MN-4 and BIS-М-LA designs.


* with M6 x 0.5 thread

BIS-1, BIS-2, BIS-MN-2, BIS-M-LA, BIS-MN-4 Sources

Source Code

Dimensions of the Source

(Working Window),mm


Source,s-1

Exposure Dose Rate of X- ray and Gamma

Emission at a Distance 0.5 m from the Source Surface

(not more than),A/kg

Maximum Content Activity of Sr90+Y90

in a Source

Diameter,D (d)

Height,H Bq mCi

1BIS-1

12.7 (5.5) 19(2.70 ± 1.20)·107 6.7·10-11 0.9·109 25

BIS-2 (1.00 ± 0.40)·106 — 3.3·107 0.9

2 BIS-MN-2 6 (1.5)

7,5(3.80 ± 1.30)·107 8.5·10-11 1.1·109 30

3 BIS-MN-4 6* (1.5)

2 BIS-M-LA 6 (1.5) (2.2 ± 1.00)·108 1.0·10-9 11.1·109 300

Sr90 +Y90

beta-emission


2. T-13 Source1. T-1 – T-4, T-17 – T-20, T-22 Sources

3. T-21 Source


ApplicationTo check operability of dosimetry and radiometric equipment when used in sealed shutter-type detectors.

Notes:Integrity Rating of the sources is “ISO/99/С24242” according to the State Standard GOST R 52241 (ISO 2919).The sources are leak tested by wiping the entire surface with a wet swab; pass limit – 1500 Bq.

T-1 – T-4, T-13, T-17 – T-22 Sources


Source Dimensions, mm External Beta-Emission of the

Source ,s-1

Content Activity of Ra-dionuclides in a Source,

Bq (Ci),not more than

Diameter (Length)

D (L)

Height(Width),

H (W)

1

Т-1

Sr90+Y90

14 0.35 (1.0 – 3.0)·106 6.6·106 (1.8·10-4)

Т-2 14 0.35 (1.0 – 3.0)·105 6.6·105 (1.8·10-5)

Т-3 14 0.35 (1.5 – 4.5)·104 1.0·105 (2.7·10-6)

Т-4 14 0.35 (1.0 – 3.0)·103 6.6·103 (1.8·10-7)

2 Т-13 42 0.35 (6) (1.0 – 3.0)·103 6.6·103 (1.8·10-7)

1

Т-17 14 0.35 (1.0 – 3.0)·104 6.6·104 (1.8·10-6)

Т-18 14 0.35 (4.0 – 12.0)·103 2.7·104 (7.3·10-7)

Т-19 14 0.35 (4.0 – 12.0)·104 2.7·105 (7.3·10-6)

Т-20 14 0.35 (4.0 – 12.0)·105 2.7·106 (7.3·10-5)

3 Т-21 8 0.35 (5) (5.0 – 15.0)·102 3.3·103 (8.9·10-8)

1 Т-22 14 0.35 (6.0 – 18.0)·104 4.1·105 (1.1·10-5)

Sr90 +Y90

beta-emission


3. GIID-10-0,5 – GIID-10-4 Sources

4. GIID-11-0,5 – GIID-11a-4 Sources


1. GIID-1 – GIID-8-3 Sources

GIID-1 – GIID-7: 12Х18Н10T steelGIID-4М,GIID-8:

02Х17Н14М2 steel

Iridium slug or discs

H

H

h

hD

D

d

d

02Х17Н14М2 steel

Iridium slug

spacer

02Х17Н14М2 steel

Iridium slug

02Х17Н14М2 steel


spacerH

H

D

D

d

d

h

h

Notes:Capsules are argon-arc (TIG) seal welded.Integrity Rating according to the State Standard GOST R 52241 (ISO 2919) is “ISO/99/C65546” for GIID-1 – GIID-5, “ISO/99/E65546” for GIID-6, GIID-7, and according to the State Standard GOST 25926 (ISO 2919) С 63545 for GIID-8-0,5 GIID-8-3, GIID-9-0,5 GIID-9-2, GIID-10-0,5 – GIID-10-3, GIID-11-0,5 – GIID-11-3, GIID-11a-0,5 – GIID 11a-3, Е 63545 for GIID-10-4, GIID 11 4, GIID-11а-4.The sources are leak tested by immersion test according to the State Standard GOST R 51919 (ISO 9978); pass limit – 200 Bq.The source designs are Special Form certified.

Principal Technical SpecificationsActive component in the form of Iridium-192 metal discs or slugs encapsulated in a corrosion-resistant steel capsule.The designated working life of the sources is 3 years from the date of QC final acceptance.

ApplicationGamma radiography

Ir192 gamma-emission


GIID-1 – GIID-11а-4 Source Series

Source Code

Dimensions of the Source(Active Component),

mmNominal Exposure Dose Rate at a Distance 1 m

from the Source Working Surface,

A/kg

Maximum Content Activity of Ir192 in a Source

Diameter,D (d)

Height(Thickness),

H (h)TBq Ci

1

GIID-1 4 (0.5) 5 (0.5) 5.8∙10-8 0.10 2.8GIID-2 4 (1) 5 (1) 2.60∙10-7 0.59 16GIID-3 4 (1.5) 5 (1.5) 7.8∙10-7 1.6 44GIID-4 4 (2) 5 (2) 12.8∙10-7 3.59 9.7∙101

GIID-4М 4 (2) 6 (3) 1.35∙10-6 5.74 1.55∙102

GIID-5 5 (3) 6 (3) 2.60∙10-6 10.8 2.93∙102

GIID-6 6 (4) 7 (4) 7.8∙10-6 28.8 7.8∙102

GIID-7 8 (6) 9 (6) 12.8∙10-6 63 17.14∙102

GIID-8-0,5 4.5 (0.5) 8 (0.5) 5.8∙10-8 0.10 2.8GIID-8-1 4.5 (1) 8 (1) 2.60∙10-7 0.59 16GIID-8-1,5 4.5 (1,5) 8 (1.5) 7.8∙10-7 1.7 45GIID-8-2 4.5 (2) 8 (2) 12.8∙10-7 3.7 9.9∙101

GIID-8-3 4.5 (3) 8 (3) 2.60∙10-6 11 2.98∙102

2

GIID-9-0,5 6.2 (0,5) 15.1 (0.5) 5.8∙10-8 0.10 2.8GIID-9-1 6.2 (1) 15.1 (1) 2.60∙10-7 0.59 16GIID-9-1,5 6.2 (1.5) 15.1 (1.5) 7.8∙10-7 1.6 44GIID-9-2 6.2 (2) 15.1 (2) 12.8∙10-7 3.7 9.9∙101

3

GIID-10-0,5 6.4 (0,5) 26.8 (0.5) 5.8∙10-8 0.10 2.8GIID-10-1 6.4 (1) 26.8 (1) 2.60∙10-7 0.59 16GIID-10-1,5 6.4 (1,5) 26.8 (1.5) 7.8∙10-7 1.6 44GIID-10-2 6.4 (2) 26.8 (2) 12.8∙10-7 3.7 9.9∙101

GIID-10-3 6.4 (3) 26.8 (3) 2.60∙10-6 11 2.98∙102

GIID-10-4 6.4 (4) 26.8 (4) 7.8∙10-6 29 7.73∙102

4

GIID-11-0,5 7.15 (0.5) 19.7 (0.5) 5.8∙10-8 0.11 2.9GIID-11-1 7.15 (1) 19.7 (1) 2.60∙10-7 0.60 16GIID-11-1,5 7.15 (1.5) 19.7 (1.5) 7.8∙10-7 1.7 46GIID-11-2 7.15 (2) 19,7 (2) 12.8∙10-7 3.8 10.4∙101

GIID-11-3 7.15 (3) 19,7 (3) 2.60∙10-6 12 3.15∙102

GIID-11-4 7.15 (4) 19.7 (4) 7.8∙10-6 31 8.47∙102

GIID-11а-0,5 6 (0,5) 19.7 (0,5) 5.8∙10-8 0.11 3,0GIID-11а-1 6 (1) 19.7 (1) 2.60∙10-7 0.63 17GIID-11а-1,5 6 (1,5) 19.7 (1,5) 7.8∙10-7 1.8 48GIID-11а-2 6 (2) 19.7 (2) 12.8∙10-7 3.8 10.4∙101

GIID-11а-3 6 (3) 19.7 (3) 2.60∙10-6 12 3.15∙102

GIID-11а-4 6 (4) 19.7 (4) 7.8∙10-6 31 8.51∙102






1. GIID-12-0,5 – GIID-12a-4 Sources

02Х17Н14М2 steel


spacerH

Dd

h

H

h

02Х17Н14М2 steel


Dd

H

02Х17Н14М2 steel


h

Dd

Notes:Capsules are argon-arc (TIG) seal welded.Integrity Rating of the sources according to the State Standard GOST 25926 (ISO 2919) is С 63545 for GIID 12 0,5 –GIID-12-3, GIID-12a-0,5 –GIID-12a-3, GIID-13-0,5 –GIID-13-3, GIID-14-0,5 – GIID-14-3, GIID-15-0,5 – GIID-15-3, and E 63545 for GIID-12-4, GIID-12a-4, GIID-15-4.The sources are leak tested by immersion test according to the State Standard GOST R 51919 (ISO 9978); pass limit – 200 Bq.The source designs are Special Form certified.

Principal Technical SpecificationsActive component in the form of Iridium-192 metal discs or slugs encapsulated in a corrosion-resistant steel capsule.The designated working life of the sources is 3 years from the date of QC final acceptance.

ApplicationGamma radiography


H

D

h

02Х17Н14М2 steel


d


GIID-12-0,5 – GIID-15-4 Source Series

Source Code

Dimensions of the Source (Active Component), mm Nominal Exposure Dose

Rate at a Distance 1 m from the Source Working Surface,

A/kg

Maximum Content Activity of Ir192 in a

Source

Diameter,D (d)

Height(Thickness),

H (h)TBq Ci

1

GIID-12-0,5 6.7 (0.5) 27.2 (0.5) 5.8∙10-8 0.10 2.8GIID-12-1 6.7 (1) 27.2 (1) 2.60∙10-7 0.56 15GIID-12-1,5 6.7 (1,5) 27.2 (1.5) 7.8∙10-7 1.6 42GIID-12-2 6.7 (2) 27.2 (2) 12.8∙10-7 3.5 9.4∙101

GIID-12-3 6.7 (3) 27.2 (3) 2.60∙10-6 10 2.8∙102

GIID-12-4 6.7 (4) 27.2 (4) 7.8∙10-6 27 7.26∙102

GIID-12а-0,5 6 (0.5) 27.2 (0.5) 5.8∙10-8 0.10 2.8GIID-12а-1 6 (1) 27.2 (1) 2.60∙10-7 0.56 15GIID-12а-1,5 6 (1.5) 27.2 (1.5) 7.8∙10-7 1.6 42GIID-12а-2 6 (2) 27.2 (2) 12.8∙10-7 3.4 9.2∙101

GIID-12а-3 6 (3) 27.2 (3) 2.60∙10-6 10 2.77∙102

GIID-12а-4 6 (4) 27.2 (4) 7.8∙10-6 26 7.14∙102

2

GIID-13-0,5 5 (0.5) 7.5 (0.5) 5.8∙10-8 0.11 3.0GIID-13-1 5 (1) 7.5 (1) 2.60∙10-7 0.63 17GIID-13-1,5 5 (1.5) 7.5 (1.5) 7.8∙10-7 1.8 47GIID-13-2 5 (2) 7.5 (2) 12.8∙10-7 3.8 10.4∙101

GIID-13-3 5 (3) 7.5 (3) 2.60∙10-6 12 3.15∙102

3

GIID-14-0,5 5.2 (0.5) 15.1 (0.5) 5.8∙10-8 0.11 3.0GIID-14-1 5.2 (1) 15.1 (1) 2.60∙10-7 0.63 17GIID-14-1,5 5.2 (1.5) 15.1 (1.5) 7.8∙10-7 1.8 48GIID-14-2 5.2 (2) 15.1 (2) 12.8∙10-7 3.7 9.9∙101

GIID-14-3 5.2 (3) 15.1 (3) 2.60∙10-6 11 2.98∙102

4

GIID-15-0,5 5.55 (0.5) 15.2 (0.5) 5.8∙10-8 0.10 2.8GIID-15-1 5.55 (1) 15.2 (1) 2.60∙10-7 0,56 15GIID-15-1,5 5.55 (1.5) 15.2 (1.5) 7.8∙10-7 1,6 42GIID-15-2 5.55 (2) 15.2 (2) 12.8∙10-7 3,7 9.9∙101

GIID-15-3 5.55 (3) 15.2 (3) 2.60∙10-6 11 2.98∙102

GIID-15-4 5.55 (4) 15.2 (4) 7.8∙10-6 31 8.28∙102



2. IGI-C-4 – IGI-C-14 Sources1. IGI-C-3-1 – IGI-C-3-22 Sources

4. IGI-C-21-1 Source3. IGI-C-16-1 – IGI-C-20 Sources

5. IGI-C-22-1 Source

12Х18Н10T steel

active component

H

H H

h h

h h

h

D D

D D

D

d d

d d

d

02Х17Н14М2 steel/XH65MB alloy

for IGI-C-8, IGI-C-9

12Х18Н10T steel

active component

02Х17Н14М2 steel

active component

02Х17Н14М2 steel

02Х17Н14М2 steel

active component

02Х17Н14М2 steel

active component

02Х17Н14М2 steel

H

02Х17Н14М2 steel

H

Principal Technical SpecificationsSingle or double encapsulation of Caesium-137 incorporated into pelletized powder or granule of zeolite or glass-melt.The designated working life of the sources is 15 years from the manufacturing date.

ApplicationGamma radiography, irradiation facilities, radioisotope instruments for process control.

Notes:Outer and inner capsules are argon-arc (TIG) seal welded.Integrity Rating according to the State Standard GOST R 52241 (ISO 2919) is “ISO/99/С65545” for IGI-C-3-1 – IGI-C-3-22, IGI-C-4-1 – IGI-4-6, “ISO/99/С65546” for IGI-C-5-1, IGI C-10-1, “ISO/99/E65546” for IGI-C-5-2 – IGI-C-9-1, IGI-C-11-1 – IGI-C-22-1. Nominal value of Cs-137 content activity is stated for IGI-C-3-12 – IGI-C-3-22; potential deviation of activity from the nominal values is ±15 %.The sources are leak tested by immersion test according to the State Standard GOST R 51919 (ISO 9978); pass limit – 185 Bq. IGI-C-8, IG-C-9, IGI-C-12, IGI-C-13, IGI-C-16 – IGI-C-22 are additionally leak tested by vacuum bubble and helium pressurisation tests.The source designs are Special Form certified.

Cs137 gamma-emission


IGI-C Source Series

Source Code

Dimensions of the Source (Active Component), mm

Nominal Exposure Dose Rate at a Distance 1 m from the Source

Working Surface, A/kg

Cs137 Content Activity in a SourceBq (Ci)Diameter,

D (d)Height,

H (h)IGI-C-3-1

6.0 (4.5) 10.0 (6.1)

3.00∙10-12 4.1∙106 – 8.1∙106 (1.10∙10-4 – 2.20∙10-4)IGI-C-3-2 9.6∙10-12 0.85∙107 – 1.59∙107 (2.30∙10-4 – 4.30∙10-4)IGI-C-3-3 1.50∙10-11 2.11∙107 – 4.07∙107 (0.57∙10-3 – 1.10∙10-3)IGI-C-3-4 3.10∙10-11 4.4∙107 – 8.1∙107 (1.20∙10-3 – 2.20∙10-3)IGI-C-3-5 6.0∙10-11 0.85∙108 – 1.59∙108 (2.30∙10-3 – 4.30∙10-3)IGI-C-3-6 1.90∙10-10 1.70∙108 – 3.00∙108 (4.6∙10-3 – 8.1∙10-3)IGI-C-3-7 1.00∙10-10 1.41∙108 – 2.66∙108 (3.8∙10-3 – 7.2∙10-3)IGI-C-3-8 3.76∙10-10 3.48∙108 – 6.29∙108 (0.94∙10-2 – 1.70∙10-2)IGI-C-3-9 8.70∙10-10 0.70∙109 – 1.18∙109 (1.90∙10-2 – 3.20∙10-2)IGI-C-3-10 1.50∙10-9 1,70∙109 – 3,00∙109 (4,6∙10-2 – 8.1∙10-2)IGI-C-3-11 2.10∙10-9 2.40∙109 – 4.20∙109 (0.64∙10-1 – 1.10∙10-1)IGI-C-3-12 2.70∙10-9 4.44∙109 (1.20∙10-1 )IGI-C-3-13 3.15∙10-9 5.18∙109 (1.40∙10-1 )IGI-C-3-14 4.05∙10-9 6.66∙109 (1.80∙10-1 )IGI-C-3-15 5.40∙10-9 8.88∙109 (2.40∙10-1 )IGI-C-3-16 6.75∙10-9 1.11∙1010 (3.00∙10-1 )IGI-C-3-17 8.55∙10-9 1.41∙1010 (3.80∙10-1 )IGI-C-3-18 1.13∙10-8 1.85∙1010 (5.00∙10-1 )IGI-C-3-19 1.46∙10-8 2.41∙1010 (6.50∙10-1 )IGI-C-3-20 1.91∙10-8 3.15∙1010 (8.50∙10-1 )IGI-C-3-21 2.25∙10-8 3.70∙1010 (1.00)IGI-C-3-22 2.93∙10-8 4.81∙1010 (1.300)IGI-C-4-1

8.0 (4.9) 12.0 (5.5)

3.10∙10-9 3.48∙109 – 6.29∙109 (0.94∙10-1 – 1.70∙10-1)IGI-C-4-2 6.00∙10-9 0.67∙1010 – 1.18∙1010 (1.80∙10-1 – 3.20∙10-1)IGI-C-4-3 1.50∙10-8 1.67∙1010 – 2.96∙1010 (4.5∙10-1 – 8.0∙10-1)IGI-C-4-4 2.80∙10-8 3.15∙1010 – 5.55∙1010 (0.85 – 1.50)IGI-C-4-5 6.00∙10-8 0.67∙1011 – 1.18∙1011 (1.80 – 3.20)IGI-C-4-6 1.05∙10-7 1.15∙1011 – 2.07∙1011 (3.10 – 5.60)IGI-C-5-1

16.0 (10.0)18.0 (9.0)

3.10∙10-7 3.48∙1011 – 6.29∙1011 (0.94∙101 – 1.70∙101)IGI-C-5-2 7.35∙10-7 0.85∙1012 – 1.52∙1012 (2.30∙101 – 4.10∙101)IGI-C-6-1 24.0 (15.0) 1.20∙10-6 1.44∙1012 – 2.55∙1012 (3.9∙101 – 6.9∙101)IGI-C-7-1

19.0 (15.0) 31.0 (22.0)3.10∙10-6 4.1∙1012 – 7.0∙1012 (1.10∙102 – 1.90∙102)

IGI-C-7-2 3.65∙10-6 4.8∙1012 – 8.5∙1012 (1.30∙102 – 2.30∙102)IGI-C-8-1

35.0 (31.0) 48 (39.0)1.20∙10-5 1.74∙1013 – 3.03∙1013 (4.7∙102 – 8.2∙102)

IGI-C-8-2 2.05∙10-5 2.92∙1013 – 5.18∙1013 (0.79∙103 – 1.40∙103)IGI-C-9-1 38 (33) 49 (40) 2.90∙10-5 4.1∙1013– 7.4∙1013 (1.10∙103 –2.00∙103)IGI-C-10-1 11 (7) 16.5 (7.5) 2.90∙10-7 3.48∙1011–5.92∙1011 (0.94∙101 –1.6∙101)IGI-C-11-1

15 (11)25 (16) 1.55∙10-6 1.81∙1012–3.22∙1012 (4.9∙101 –8.7∙101)

IGI-C-12-181.5 (72.5)

7.00∙10-6 0.81∙1013–1.44∙1013(2.20∙102 – 3.90∙102)IGI-C-13-1 20 (16) 1.50∙10-5 1.78∙1013–3.18∙1013 (4.8∙102 –8.6∙102)IGI-C-14-1

11.5 (8.5) 84 (75)4.30∙10-6 5.0∙1012– 8.9∙1012 (1.35∙102 –2.40∙102)

IGI-C-14-2 3.10∙10-6 3.48∙1012– 6.29∙1012 (0.94∙102 –1.70∙102)IGI-C-14-3 1.30∙10-6 1.48∙1012– 2.63∙1012(4.0∙101 – 7.1∙101)IGI-C-16-1 12.49max (9.06) 17.85max (9.95) 6.50∙10-7 0.81∙1012– 1.30∙1012 (2.20∙101 –3.50∙101)IGI-C-17-1 14.69max (11.15) 20.4max (12.0) 1.02∙10-6 1.30∙1012– 2.04∙1012 (3.50∙101 –5.50∙101)IGI-C-18-1 17.49max (14.06) 22.9max (14.5) 2.19∙10-6 2.81∙1012– 4.44∙1012 (0.76∙102 –1.20∙102)IGI-C-19-1 21.29max (17.86) 26.35max (18.0) 4.32∙10-6 5.6∙1012– 8.9∙1012 (1.50∙102 –2.40∙102)IGI-C-20-1 27.1max (23.65) 28.4max (20.0) 8.45∙10-6 1.11∙1013– 1.78∙1013 (3.00∙102 –4.80∙102)IGI-C-21-1 30.15max (25.6) 70.35max (52.8) 2.00∙10-5 3.48∙1013–5.18∙1013 (0.94∙103 –1.40∙103)IGI-C-22-1 36.15max (32.25) 65.35max (57.35) 3.55∙10-5 5.9∙1013–9.6∙1013(1.60∙103 – 2.60∙103)




2. М37С03-01 – М37С04-27, М37С09-01 –М37С09-39, М37С23-30 –М37С23-58 М37С24-41 – М37С24-44* Sources

1. М37С02-01 – М37С02-27, М37С08-01 –М37С08-39, М37С11-01 –М37С11-53 Sources

4. М37С21 Source3. М37С16 – М37С20 Sources

5. М37С22 Source

steel to ISO 5832-1/ 02Х17Н14М2-ID/

02Х17Н14М2-IDD

active component

H

H H

h h

h h

h

D D

D D

D

d d

d d

d

12Х18Н10Т steel

active component

active componentactive component

steel 02Х17Н14М2

active component

H

H

Principal Technical SpecificationsSingle or double encapsulation of Caesium-137 incorporated into pelletized powder or granule of zeolite or glass-melt.The recommended working life is 15 years from the date of QC final acceptance.

ApplicationGamma radiography, irradiation facilities, radioisotope instruments for process control, oil well logging

Notes:Outer and inner capsules are argon-arc (TIG) seal welded.Integrity Rating according to the State Standard GOST R 52241 (ISO 2919) is “ISO/99/С65545” for М37С08, М37С09, М37С11, “ISO/99/С66545” for М37С02, М37С03, М37С04, М37С23, “ISO/99/С65546” for М37С16 – М37С22, “ISO/99/С56522” for М37С24.The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by:a) vacuum bubble test; pass criterion – no bubbles observed;b) immersion test; pass limit – 185 Bq.М37С16 – М37С22 sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by:a) vacuum bubble test; pass criterion – no bubbles observed;b) helium pressurisation test; pass limit –10 -2 cm3·Pa·s-1.The source designs are Special Form certified.

* MP35N steel for М37С24-41 – М37С24-44 sources


02Х17Н14М2-IDD


02Х17Н14М2-IDD


02Х17Н14М2-IDD


02Х17Н14М2-IDD


02Х17Н14М2-IDD


02Х17Н14М2-IDD


Cs-137 Gamma-Sources M37C02 – M37C04, М37С08, M37C09, M37C11, M37C23, М37С24

Source Code

Dimensions of the Source (Active Component), mm Air Kerma Rate at a Distance 1 m

from the Source Bottom End Face, nGy/s

Nominal Content Activity of Cs137 in a Source

CiDiameter,D (d)

Height,H (h)

М37С02-01

4.55(3)

6.2(3)

0.68 – 0.93 1.00∙10-3

М37С02-02 1.37 –1.85 2.00∙10-3

М37С02-03 2.05 – 2.78 3.00∙10-3

М37С02-05 3.42 – 4.63 5 .00∙10-3

М37С02-07 4.83 – 6.52 7.0∙10-3

М37С02-09 6.8 – 9.3 1.00∙10-2

М37С02-13 13.7 – 18.5 2.00∙10-2

М37С02-15 17.2 – 23.2 2.50∙10-2

М37С02-16 20.5 – 2.8 3.00∙10-2

М37С02-18 27.4 – 37.0 4.00∙10-2

М37С02-19 34.2 – 46.3 5.00∙10-2

М37С02-21 48.3 – 65.2 7.00∙10-2

М37С02-22 54.7 – 74.1 8.00∙10-2

М37С02-23 68 – 93 1.00∙10-1

М37С02-25 103 – 139 1.50∙10-1

М37С02-27 137 – 185 2.00∙10-1

М37С03-01

12.8(3)

19.2(3)

0.68 – 0.92 1.00∙10-3

М37С03-02 1.35 – 1.83 2.00∙10-3

М37С03-03 2.03 – 2.75 3.00∙10-3

М37С03-05 3.39 – 4.58 5.00∙10-3

М37С03-07 4.78 – 6.46 7.0∙10-3

М37С03-09 6.8 – 9.2 1.00∙10-2

М37С03-13 13.6 – 18.3 2.00∙10-2

М37С03-15 17.0 – 23.0 2.50∙10-2

М37С03-16 20.3 – 27.5 3.00∙10-2

М37С03-18 27.1 – 36.7 4.00∙10-2

М37С03-19 33.9 – 45.8 5.00∙10-2

М37С03-21 47.8 – 64.6 7.0∙10-2

М37С03-22 54.2 – 73.3 8.0∙10-2

М37С03-23 68 – 92 1.00∙10-1

М37С03-25 102 – 138 1.50∙10-1

М37С03-27 136 – 183 2.00∙10-1

М37С04-016.05(3)

8.15(3)

0.68 – 0.93 1.00∙10-3

М37С04-02 1.37 – 1.85 2.00∙10-3

М37С04-03 2.05 – 2.78 3.00∙10-3



Source Code




CiDiameter,D (d)

Height,H (h)

М37С04-05

6.05(3)

8.15(3)

3.42 – 4.63 5.00∙10-3

М37С04-07 4.83 –6.52 7.00∙10-3

М37С04-09 6.8 – 9.3 1.00∙10-2

М37С04-13 13.7 – 18.5 2.00∙10-2

М37С04-15 17.2 – 23.2 2.50∙10-2

М37С04-16 20.5 – 27.8 3.00∙10-2

М37С04-18 27.4 – 37.0 4.00∙10-2

М37С04-19 34.2 – 46.3 5.00∙10-2

М37С04-21 48.3 – 65.2 7.0∙10-2

М37С04-22 54.7 – 74.1 8.0∙10-2

М37С04-23 68 – 93 1.00∙10-1

М37С04-25 103 – 139 1.50∙10-1

М37С04-27 137 – 185 2.00∙10-1

М37С08-01

6,2(4.49)

10(6.1)

0.69 – 0.94 1.00∙10-3

М37С08-02 1.38 – 1.87 2.00∙10-3

М37С08-03 2.07 – 2.81 3.00∙10-3

М37С08-05 3.46 – 4.68 5.00∙10-3

М37С08-07 4.88 – 6.59 7.0∙10-3

М37С08-09 6.9 – 9.4 1.00∙10-2

М37С08-13 13.8 – 18.7 2.0∙10-2

М37С08-15 17.3 – 23.4 2.50∙10-2

М37С08-16 20.7 – 28.1 3.00∙10-2

М37С08-18 27.7 – 37.4 4.00∙10-2

М37С08-19 34.6 – 46.8 5.00∙10-2

М37С08-21 48.8 – 65.9 7.0∙10-2

М37С08-22 55.3 – 74.8 8.0∙10-2

М37С08-23 69 – 94 1.00∙10-1

М37С08-25 104 – 141 1.50∙10-1

М37С08-27 138 – 187 2.00∙10-1

М37С08-28 173 – 234 2.50∙10-1

М37С08-29 207 – 281 3.00∙10-1

М37С08-30 242 – 328 3.50∙10-1

М37С08-33 346 – 468 5.00∙10-1

М37С08-35 521 – 700 7.5∙10-1

М37С08-37 691 – 935 1.00М37С08-39 935 – 1260 1.35М37С09-01

8(4.9)

12(5.5)

0.69 – 0.94 1.00∙10-3

М37С09-02 1.38 – 1.87 2.00∙10-3

М37С09-03 2.07 – 2.81 3.00∙10-3

М37С09-05 3.46 – 4.68 5.00∙10-3

М37С09-07 4.88 – 6.59 7.0∙10-3



Source Code




CiDiameter,D (d)

Height,H (h)

М37С09-09

8(4.9)

12(5.5)

6.9 – 9.4 1.00∙10-2

М37С09-13 13.8 –18.7 2.00∙10-2

М37С09-15 17.3 – 23.4 2.50∙10-2

М37С09-16 20.7 – 28.1 3.00∙10-2

М37С09-18 27.7 – 37.4 4.00∙10-2

М37С09-19 34.6 – 46.8 5.00∙10-2

М37С09-21 48.8 – 65.9 7.0∙10-2

М37С09-22 55.3 – 74.8 8.0∙10-2

М37С09-23 69 – 94 1.00∙10-1

М37С09-25 104 – 141 1.50∙10-1

М37С09-27 138 – 187 2.00∙10-1

М37С09-28 173 – 234 2.50∙10-1

М37С09-29 207 – 281 3.00∙10-1

М37С09-30 242 – 328 3.50∙10-1

М37С09-33 346 – 468 5.00∙10-1

М37С09-35 521 – 700 7.5∙10-1

М37С09-37 691 – 935 1.00М37С09-39 935 – 1260 1.35М37С11-01

8.0+0.0

(6.2)10.0+0.0

(6.6)

0.68 – 0.93 1.00∙10-3

М37С11-02 1.37 – 1.85 2.00∙10-3

М37С11-03 2.05 – 2.78 3.00∙10-3

М37С11-05 3.42 – 4.63 5.00∙10-3

М37С11-07 4.83 – 6.52 7.0∙10-3

М37С11-09 6.8 – 9.3 1.00∙10-2

М37С11-13 13.7 – 18.5 2.00∙10-2

М37С11-15 17.2 – 23.2 2.50∙10-2

М37С11-16 20.5 – 27.8 3.00∙10-2

М37С11-18 27.4 – 37.0 4.00∙10-2

М37С11-19 34.2 – 46.3 5.00∙10-2

М37С11-21 48.3 – 65.2 7.0∙10-2

М37С11-22 54.7 – 74.1 8.0∙10-2

М37С11-23 68 – 93 1.00∙10-1

М37С11-25 103 – 139 1.50∙10-1

М37С11-27 137 – 185 2.00∙10-1

М37С11-28 172 – 232 2.50∙10-1

М37С11-29 205 – 278 3.00∙10-1

М37С11-30 240 – 325 3.50∙10-1

М37С11-33 342 – 463 5.00∙10-1

М37С11-35 515 – 692 7.5∙10-1

М37С11-37 684 – 926 1.00М37С11-39 926 – 1248 1.35М37С11-40 1031 – 1393 1.50


–0.1–0.1



Source Code




CiDiameter,D (d)

Height,H (h)

М37С11-51 8.0+0.0

(6.2)10.0+0.0

(6.6)1369 – 1852 2.00

М37С11-53 1715 – 2319 2.50М37С23-30

12.8(7.0)

19.2(12)

231 – 312 3.50∙10-1

М37С23-33 329 –445 5.00∙10-1

М37С23-35 495 – 665 7.5∙10-1

М37С23-37 658 – 890 1.00М37С23-39 890 – 1199 1.35М37С23-40 990 – 1338 1.50М37С23-51 1315 – 1779 2.00М37С23-53 1648 – 2228 2.50М37С23-55 1973 – 2669 3.00М37С23-57 2630 – 3558 4.00М37С23-58 3288 – 4448 5.00М37С24-41

11.45(6.2)

19.05(6.6)

677-917 1.00М37С24-42 1020-1379 1.50М37С24-43 1355-1833 2.00М37С24-44 1698-2295 2.50

Source Code

Dimensions of the Source (Active Component), mm Exposure Dose Rate at

a Distance 1 m from the Source Bottom End Face,

A/kg

Air Kerma Rate at a Distance 1 m from the Source Bottom

End Face, µGy/s

Cs137 Content Activity in a

SourceCiDiameter,

D (d)Height,

H (h)

М37С16 12.49 (8.66) 17.85 (9.9) (4.4615 – 6.0230)∙10-7 15.2-20.5 20.0-27.0М37С17 14.69 (10.82) 20.40 (11.9) 8.3961 ∙10-7 – 1.1047∙10-6 28.5-37.6 38.0-50.0М37С18 17.49 (13.66) 22.90 (14.4) (1.5828 – 2.0814)∙10-6 54-71 73-96М37С19 21.29 (17.42) 26.35 (17.9) (3.1214 – 4.1338)∙10-6 106-141 148-196М37С20 27.10 (22.76) 28.40 (19.9) (5.9985 – 7.6288)∙10-6 204-259 287-365М37С21 30.15 (24.7) 70.35 (52.7) (1.3760 – 1.8400)∙10-5 468-626 (0.86-1.15)∙103

М37С22 36.15 (31.4) 65.35 (56.2) (2.3517 –3.0986)∙10-5 (80-105)∙101 (1.48-1.95)∙103

Cs-137 Gamma-Sources M37C16 – M37C22

–0.1–0.1


1. IGI-C-32, IGI-C-33 Sources

4. IGI-C-41 Source

3. IGI-C-36 – IGI-C-40 Sources

2. IGI-C-34 Source

h

Dd

active component

02Х17Н14М2-ID (-IDD) steel

Н

h


Dd

active componentН

Dd

Dd

active component

active component



hН

hН

Notes:Capsules are argon-arc (TIG) seal welded.Integrity Rating of the sources is “ISO/99/E65546” according to the State Standard GOST R 52241 (ISO2919). Integrity Rating of IGI-C-32, IGI-C-33 is “ISO/99/E65646(5,7)” according to the State Standard GOST R 52241 (ISO 2919).The sources are leak tested according to the State StandardGOST R 51919 (ISO 9978) by:a) vacuum bubble test; pass criterion – no bubbles observed;b) helium pressurisation test; pass limit – 1.0 cm3·Pa·s-1.The source designs are Special Form certified.

Principal Technical SpecificationsDouble encapsulation of Caesium-137 incorporated into glass.The designated working life of the sources is 7 years from the date of QC final acceptance.

ApplicationRadiation equipment and instruments.





5. IGI-C-42 Source

hH

D d


active component

02Х17Н14М2-ID (-IDD) steel)



IGI-C-32 – IGI-C-42 Source Series

Source Code Radio-nuclide

Dimensions of the Source(Active Component),

mmNominal Exposure Dose Rate at a Distance 1 m


A/kg

Maximum Cs137 Content Activity in a Source

Diameter,D (d)

Height,H (h) Bq Ci

1IGI-C-32

Cs137

12.77 (8.0) 271.50 (83.4*) 1.08∙10-5 – 1.44∙10-5 2.52∙1013 6.82∙102

IGI-C-33 17.52 (12.7) 271.50 (83.4*) 2.47∙10-5 – 3.29∙10-5 5.62∙1013 1.52∙103

2 IGI-C-34 39.92 (35.5) 43.31 (33.2) 2.04∙10-5 – 3.67∙10-5 7.21∙1013 1.95∙103

3

IGI-C-36 12.49 (8.9) 17.85 (9.5) 2.82∙10-7 – 7.42∙10-7 1.29∙1012 3.50∙101

IGI-C-37 14.69 (11.1) 20.40 (11.5) 5.23∙10-7 – 1.13∙10-6 2.00∙1012 5.40∙101

IGI-C-38 17.49 (13.9) 22.90 (14.0) 1.09∙10-6 – 2.46∙10-6 4.44∙1012 1.20∙102

IGI-C-39 21.29 (17.7) 26.35 (17.5) 2.07∙10-6 – 4.79∙10-6 8.88∙1012 2.40∙102

IGI-C-40 27.10 (23.5) 28.40 (19.5) 4.10∙10-6 – 9.41∙10-6 1.76∙1013 4.75∙102

4 IGI-C-41 30.15 (25.5) 70.35 (52.3) 1.02∙10-5 – 2.10∙10-5 5.33∙1013 1.44∙103

5 IGI-C-42 36.15 (32.1) 65.35 (56.8) 1.55∙10-5 – 3.71∙10-5 9.58∙1013 2.59∙103

*Dimension is stated for one of the three inner capsules



Notes:Outer and inner capsules are argon-arc (TIG) seal welded.Integrity Rating according to the State Standard GOST R 52241 (ISO 2919) is “ISO/99/С65545” for GID-C-1, GID-C-2, “ISO/99/С65546” for GID-C-3-1, “ISO/99/Е65546” for GID-C-4-1 – GID C 6 1.Integrity Rating of IMGIC-1 – IMGIC-2 is С 66646 to the State Standard GOST 25926 (ISO 2919).The sources are leak tested by immersion test according to the State Standard GOST R 51919 (ISO 9978); pass limit - 185 Bq.The source designs are Special Form certified.

Principal Technical SpecificationsSingle or double encapsulation of Caesium-137 incorporated into pelletized powder, or zeolite granule, or glass bead. The designated working life that starts from the manufacturing date, is 7 years for GID-C-1-1, and 15 years for the other source designs.

ApplicationGamma radiography, irradiation facilities, radioisotope instruments for process control.

4. IMGIC-2-1 – IMGIC-2-300 Sources

3. IMGIC-1-1 – IMGIC-1-300 Sources

2. GID-C-2-1 – GID-C-6-1 Sources1. GID-C-1-1 Source

02Х17Н14М2 steel

active component

H

h

D

D

D

d

d

d

02Х17Н14М2 steel

12Х18Н10T steel

active component

H

h

Dd

02Х17Н14М2 steel

02Х17Н14М2 steel

active component02Х17Н14М2 steel

02Х17Н14М2 steel

active component

H

h

h


H


GID-C, IMGIC Source Series

Source Code


Nominal Exposure Dose Rate at a

Distance 1 m from the Source Surface,

A/kg

Maximum Cs137 Content Activity in a Source

Diameter,D (d)

Height,H (h) Bq Ci

1 GID-C-1-1 6 (3) 10 (3) 2.30∙10-8 4.44∙1010 1.20

2

GID-C-2-1 8 (4.9) 12 (5.5) 1.05∙10-7 2.07∙1011 5.60

GID-C-3-1 10 (6) 13 (4) 1.15∙10-7 2.33∙1011 6.30

GID-C-4-1 14 (10) 19 (10) 8.00∙10-7 1.67∙1012 4.50∙101

GID-C-5-1 22 (18) 26 (16.5) 4.20∙10-6 9.3∙1012 2.50∙102

GID-C-6-1 27 (23) 31 (22) 8.5∙10-6 1.89∙1013 5.10∙102

3 IMGIC-1-1 – IMGIC-1-3006.4 max (3.2) 16 max (4) 2.21∙10-11 – 6.63∙10-9 1.58∙1010 4.28∙10-1

4 IMGIC-2-1 – IMGIC-2-300



K-3, K-3A Sources

12Х18Н10Т steel

12Х18Н10Т steel

working window

active component

d

H

D

Notes:Capsules are argon-arc (TIG) seal welded.The sources successfully pass Special Form Material (SFM) tests.On agreement with a customer, compliance of the sources with SFM requirements can be verified by SFM Certificate. Integrity Rating of the sources is “ISO/99/С65546” according to the State Standard GOST R 52241 (ISO 2919).The sources are leak tested by immersion test according to the State Standard GOST R 51919 (ISO 9978); pass limit – 185 Bq.

Principal Technical SpecificationsActive component (insert with Cobalt-60 activity deposit) encapsulated in steel.The designated working life of the sources is 5 years from the date of QC final acceptance.

ApplicationTo check dose meters operability.

K-3, K-3A Sources

Source Code


Exposure Dose Rate of Gamma Emission at a

Distance 0.5 m from the Source Surface,

A/kg

Co60 Content Activity in a Source not more than

Diameter,D (d)

Height,H Bq Ci

К-330 (9.5) 4.5

(3.7±1.6)·10-14 2.2·104 5.9·10-7

К-3А (7.5±3.1)·10-14 4.4·104 1.2·10-6

Co60 gamma-emission


1. GIT-K Source Series

12Х18Н10Т steel

active component

Hh

Dd

Notes:Capsules are argon-arc (TIG) seal welded.Integrity Rating of the sources is “ISO/99/С65545” according to the State Standard GOST R 52241 (ISO 2919).The source designs are Special Form certified.The sources are leak tested by immersion test according to the State Standard GOST R 51919 (ISO 9978); pass limit – 185 Bq.

Principal Technical SpecificationsSingle encapsulation design with Cobalt-60 metal slugs as active components.The designated working life of the sources is 5 years from the date of QC final acceptance.

ApplicationIntended for gamma-therapy facilities with hose-like guide tubes for intracavitary irradiation.

Source Code

Dimensions of the Source (Active Component), mm Nominal Exposure

Dose Rate at a Distance 1 m from the Source

Working Surface,A/kg

Maximum Co60 Content Activity in a Source

DiameterD (d)

HeightH (h) Bq Ci

GIT-K-10

3 (1.4) 14 (9.9)

1.40·10-8 6.66·109 1.80·10-1

GIT-K-11 2.80·10-8 1.33·1010 3.60·10-1

GIT-K-12 5.60·10-8 2.66·1010 7.20·10-1

GIT-K Source Series

Co60 gamma-emission


02Х17Н14М2-ID (-IDD) steel12Х18Н10Т (-ID) steel for GIK-17M

4. GIK-23 Source

2. GIK-4 – GIK-12, GIK-14, GIK-17М Sources

1. GIK-1-1 – GIK-3-2, GIK-13-1 Sources


active component

Hh

Dd

12Х18Н10Т (-ID) steel

active component

Hh

Dd

02Х17Н14М2-ID (-IDD) steel for GIK-7;ХН65МВ alloy for GIK-7m

active component

Hh

d

3. GIK-7 – GIK-7m Sources

12Х18Н10Т (-ID) steel

Principal Technical SpecificationsSingle or double encapsulation of an active component in the form of Cobalt-60 metal slugs, and 12Х18Н10Т (or –ID) steel sleeves or discs that compensate the inner free void, in corrosion-resistant steel.The designated working life of the sources is 15 years from the date of QC final acceptance.

ApplicationGamma radiography, radioisotope instruments.

active component

H

D

hd

GIK Source Series

Source Code



Nominal Exposure Dose Rate at a Distance 1 m


A/kgDiameter,

D (d)Height,

H (h) Bq Ci

1

GIK-1-1

6 (3) 7 (3.3)

5.55·109 1.50·10-1 6.3·10-9

GIK-1-2 1.42·1010 3.85·10-1 1.60·10-8

GIK-1-3 1.42·1011 3.85 1.60·10-7

GIK-1-4 1.07·107 2.90·10-4 1.20·10-11

GIK-1-5 2.22·107 6.00·10-4 2.50·10-11

GIK-2-46 (4.5) 7 (4.5)

2.89·1011 7.8 3.20·10-7

GIK-2-6 2.89·1012 7.8·101 3.20·10-6

Co60 gamma-emission

D


GIK Source Series (continued)

Source Code



Nominal Exposure Dose Rate at a Distance 1 m


A/kgDiameter,

D (d)Height,

H (h) Bq Ci

1

GIK-2-7

6 (4.5)7 (4.5)

7.2·107 1.95·10-3 8.0·10-11

GIK-2-8 2.89·108 7.8·10-3 3.20·10-10

GIK-2-9 7.2·108 1.95·10-2 8.0·10-10

GIK-2-10 1.44·109 3.90·10-2 1.60·10-9

GIK-2-12 2.89·109 7.8·10-2 3.20·10-9

GIK-2-13 7.2·109 1.95·10-1 8.0·10-9

GIK-2-14 1.44·1010 3.90·10-1 1.60·10-8

GIK-2-15 2.89·1010 7.8·10-1 3.20·10-8

GIK-2-16 7.2·1010 1.95 8.0·10-8

GIK-2-17 1.44·1011 3.90 1.60·10-7

GIK-2-18 7.2·1011 1.95·101 8.0·10-7

GIK-3-111.5 (7.5)

1.85·1011 5.00 3.20·10-7

GIK-3-2 4.07·1012 1.10·102 4.01·10-6

2

GIK-4-1

11 (8)

12 (5.5)6.8·1011 1.85·101 1.25·10-6

GIK-4-2 4.81·1012 1.30·102 9.0·10-6

GIK-5-1

16.5 (9.7)

1.89·1012 5.10·101 3.20·10-6

GIK-5-2 3.74·1012 1.01·102 6.30·10-6

GIK-5-3 7.4·1012 2.00·102 1.25·10-5

GIK-5-4 1.89·1013 5.10·102 3.20·10-5

GIK-6-126.2 (21) 27 (20)

1.63·1013 4.40·102 2.50·10-5

GIK-6-2 8.0·1013 2.15·103 1.25·10-4

GIK-6-3 1.15·1014 3.10·103 1.80·10-4

3

GIK-7-1

11.2 (7.3)

81.5 (69.5)

6.8·1012 1.85·102 1.25·10-5

GIK-7-2 2.18·1013 5.90·102 4.00·10-5

GIK-7-3 4.81·1013 1.30·103 9.00·10-5

GIK-7-4 9.8·1013 2.65·103 1.80·10-4

GIK-7m-1

11.2 (7.4)

6.8·1012 1.85·102 1.25·10-5

GIK-7m-2 2.18·1013 5.90·102 4.00·10-5

GIK-7m-3 4.81·1013 1.30·103 9.00·10-5

GIK-7m-4 9.8·1013 2.65·103 1.80·10-4

2

GIK-7а-1

12.8 (10) 86 (78.4)

2.26·1013 6.10·102 4.00·10-5

GIK-7а-2 5.18·1013 1.40·103 9.0·10-5

GIK-7а-3 7.0·1013 1.90·103 1.25·10-4

GIK-7а-4 9.8·1013 2.65·103 1.75·10-4

GIK-8-1

23 (21) 22.5 (14.5)

7.8·1013 2.10·103 1.25·10-4

GIK-8-2 1.24·1014 3.35·103 2.00·10-4

GIK-8-3 1.55·1014 4.20·103 2.50·10-4

GIK-8-4 1.98·1014 5.35·103 3.20·10-4

Co60 gamma-emission


Notes:Outer and inner capsules are argon-arc (TIG) seal welded.Integrity Rating of the sources according to the State Standard GOST R 52241 (ISO 2919) is: “ISO/99/С65545” for GIK-1-1 – GIK-1-5, GIK-2-4, GIK-2-6 – GIK-2-18, GIK-3-1, GIK-3-2, GIK-13-1; “ISO/99/С65546” for GIK-4-1, GIK-4-2, GIK-5-1 – GIK-5-3, GIK-7-1, GIK-7m-1; “ISO/99/Е65545” for GIK-5-4, GIK-6-1 – GIK-6-3, GIK-7-2 – GIK-7-4, GIK-7m-2 – GIK-7m-4, GIK 7а-1 – GIK-7а-4, GIK-8-1 – GIK-8-4, GIK-9-1 – GIK-9-4, GIK-10-1 – GIK-10-3, GIK-11-1, GIK-12-1, GIK -12а-1 – GIK-12а-4, GIK-14-1, GIK-17M; “ISO/99/С63432” for GIK-23.The source designs are Special Form certified.The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by:a) immersion test; pass limit - 185 Bq (for GIK-1, GIK-2, GIK-3, GIK-13 and GIK-23 designs only);b) for the rest of the source designs: – vacuum bubble test; pass criterion - no bubbles observed; – helium pressurisation test; pass limit – 1.0 cm3·Pa·s-1.

GIK Source Series (continued)

Source Code

Dimensions of the Source (Active Compo-

nent), mmMaximum Co60 Content Activity in a

SourceNominal Exposure Dose Rate at a Distance 1 m


A/kgDiameter,

D (d)Height,

H (h) Bq Ci

2

GIK-9-1

23 (21) 33 (24.5)

1.79·1014 4.85·103 2.50·10-4

GIK-9-2 2.31·1014 6.25·103 3.20·10-4

GIK-9-3 2.89·1014 7.80·103 4.00·10-4

GIK-9-4 3.63·1014 9.80·103 5.00·10-4

GIK-10-113 (10) 26.5 (17.8)

1.72·1013 4.65·102 2.50·10-5

GIK-10-2 3.40·1013 9.2·102 5.00·10-5

GIK-10-3 4.81·1013 1.30·103 7.00·10-5

GIK-11-111 (8) 50 (40.8)

1.78·1013 4.80·102 3.20·10-5

GIK-11-2 6.8·1013 1.85·103 1.25·10-4

GIK-12-1

11 (8)

25 (18) 3.52·1013 9.5·102 6.30·10-5

GIK-12а-1

99 (90.5)

2.22·1013 6.00·102 4.00·10-5

GIK-12а-2 5.00·1013 1.35·103 9.0·10-5

GIK-12а-3 6.8·1013 1.85·103 1.25·10-4

GIK-12а-4 1.00·1014 2.70·103 1.80·10-4

GIK-13-1 4 (2.5) 5 (2.5) 8.0·1010 2.15 1.50·10-7

1 GIK-14-1 19 (15) 22 (14) 7.4·1013 2.00·103 1.25·10-4

2 GIK-17М 21 (17) 34 (26) 4.54·1014 1.23·104 6.50·10-4

4 GIK-23 3.55 (1.4) 12.6 (9.9) 4.26·1010 1.15 7.44·10-8

Co60 gamma-emission


1. GIK-A6 – GIK-A6m Sources

02Х17Н14М2 steel for GIK-6;ХН65МВ alloy for GIK-А6m

active component

H

D

Notes:Outer and inner capsules are argon-arc (TIG) seal welded.Integrity Rating of the sources is “ISO/99/Е65546(6,7)” according to the State Standard GOST R 52241 (ISO 2919).The source designs are Special Form certified.The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by:a) vacuum bubble test; pass criterion - no bubbles observed;b) helium pressurisation test; pass limit – 1.0 cm3·Pa·s-1.

Principal Technical SpecificationsDouble encapsulation of an active component in the form of Cobalt-60 metal discs or slugs.The designated working life of the sources is 20 years from the date of QC final acceptance.

ApplicationIrradiators

GIK-А6, GIK-А6m Source

Source CodeDimensions of the Sources, mm Minimum Co60 Content Activity in a Source

Diameter,D

Height,H

Bq Ci

GIK-А6, GIK-А6m 11.1max 451.6max 3.59·1014 9.70·103

Co60 gamma-emission


1. M2089 Sources

steel to ISO 5832-102Х17Н14М2-ID (-IDD)

active component

H

D

Notes:Outer and inner capsules are argon-arc (TIG) seal welded.Integrity Rating of the sources is "ISO/12/Е66646(5,7)" according to ISO 2919:2012(E).The source design is Special Form certified.The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by:a) vacuum bubble test; pass criterion - no bubbles observed;b) helium pressurisation test; pass limit – 1.0 cm3·Pa·s-1.

Principal Technical SpecificationsDouble encapsulation of an active component in the form of Cobalt-60 metal discs or slugs.The designated working life of the sources is 20 years from the date of QC final acceptance.

ApplicationIrradiators.Intended for export.

Co-60 Gamma-Sources M2089

Source Code

Dimensions of the Sources, not more than, mm

Minimum Co60 Content Activity in a Source

Diameter,D

Height,H

Bq Ci

М2089 11.10 451.6 5.55·1014 15.00·103

Co60 gamma-emission


1. GSOO.061 Source Series

Hh

Dd

Titaniumand Titanium alloys

active component

working surface

holderflexible wire rope

tail piece

Notes:Integrity Rating of the sources is "ISO/99/С53211" according to the State Standard GOST R 52241 (ISO 2919).The sources are leak tested by immersion test according to the State Standard GOST R 51919 (ISO 9978); pass limit - 200 Bq.

Principal Technical SpecificationsThe source train assembly comprises an emitter and a source holder. The holder comprises a tail piece to connect the source train assembly to the gamma-therapy facility, a flexible wire rope, and a capsule, all made of corrosion-resistant steel. The capsule envelopes the emitter, the titanium body of which encloses Cobalt-60 cylinder.The designated working life of the sources is 5 years from the date of QC final acceptance at maximum 5000 travelling cycles total (forward and back travelling).

ApplicationIntended for gamma-therapy facilities with hose-like guide tubes for intracavitary irradiation.

GSOO.061 Source Series

Source Code

Dimensions of the Source (Active Component), mm Exposure Dose Rate at

a Distance 1 m from the Source Working Surface,

A/kg


DiameterD (d)

HeightH (h) Bq Ci

GSOO.061.1

1.6 (0.8) 11.5 (5)

22.4 – 56.0 2.28·1010 0.617GSOO.061.2 56 – 112 4.56·1010 1.23GSOO.061.3 112 – 224 9.1·1010 2.47GSOO.061.4 224 – 448 1.82·1011 4.93

Co60 gamma-emission


4. IGIA-12, IGIA-13 Sources

3. IGIA-9 – IGIA-11 Sources

2. IGIA-6-1 – IGIA-8 Sources

1. IGIA-1m – IGIA-5m-1 Sources

02Х17Н14М2 steel

active component

D

H

02Х17Н14М2 steel

active componentspacer

H

d

D

02Х17Н14М2 steel

active componentspacer

H

D

d

D

H

d

12Х18Н10T-ID (-IDD) steel

d

Notes:Source capsules are argon-arc (TIG) seal welded.Integrity Rating of the sources is "ISO/99/С65445" according to the State Standard GOST R 52241 (ISO 2919).The source designs are Special Form certified.The sources are leak tested by immersion test according to the State Standard GOST R 51919 (ISO 9978); pass limit – 185 Bq.

Principal Technical SpecificationsAmericium-241 incorporated into ceramic pellet for IGIA-1m – IGIA-5m sources or glass for the other source designs and encapsulated in corrosion-resistant steel.The designated working life of the sources is 15 years from the date of QC final acceptance.


Am241 gamma-emission


IGIA Source Series

Source Code

Dimensions of the Source(Diameter of the Working

Window), mmPhoton Flux Density

at a Distance 1 m from the Working Window

Centre, s-1·cm-2

Maximum Am241 Content Activity in a Source

Diameter,D (d)

Height,H Bq Ci

1

IGIA-1m

6 (4)

6.5

8.6±2,6 5.3·106 1.4·10-4

IGIA-1m-1 (8.6±2.6)·101 5.3·107 1.4·10-3

IGIA-1m-2 (4.3±1.3)·102 2.9·108 7.8·10-3

IGIA-1m-3 (8.6±2.6)·102 5.3·108 1.4·10-2

IGIA-1m-4 (2.20±0.66)·103 1.2·109 3.2·10-2

IGIA-1m-5 (3.60±1.08)·103 3.9·109 1.0·10-1

IGIA-2m 8 (6) (8.0±2.4)·103 9.1·109 2.5·10-1

IGIA-3m 10 (8) (1.40±0.42)·104 1.8·1010 4.8·10-1

IGIA-4m12 (10)

6.5

(6.7±2.0)·103 5.2·109 1.4·10-1

IGIA-4m-1 (2.20±0.66)·104 2.6·1010 7.0·10-1

IGIA-5m20 (18)

(2.30±0.69)·104 1.6·1010 4.3·10-1

IGIA-5m-1 (7.0±2.1)·104 8.3·1010 2.24

2

IGIA-6-1

8 (4,2)5

(8.0±2.4)·101 4.7·107 1.3·10-3

IGIA-6-2 (2.5±0.75)·102 1.7·108 4.6·10-3

IGIA-6-3 (8.0±2.4)·102 4.7·108 1.3·10-2

IGIA-810,8 (7,6)

(5.3±1.6)·103 4.1·109 1.1·10-1

3

IGIA-9

6

(5.3±1.6)·103 4.1·109 1.1·10-1

IGIA-10 15 (11,6) (1.50±0.45)·104 1.3·1010 3.5·10-1

IGIA-11 22 (18) (2.80±0.84)·104 2.1·1010 5.7·10-1

4

IGIA-12 30 (25) (5.0±1.5)·104 4.1·1010 1.11

IGIA-13 36 (29,5) 8 (1.20±0.36)·105 1.3·1011 3.51

IGIA-14 45 (40) 8 (2.00±0.20)·105 2.5·1011 6.8

Am241 gamma-emission


3. IBN-28 Source

2. IBN-13 – IBN-27 Sources1. IBN-1 – IBN-12 Sources

12Х18Н10T (-ID) steel

active component

Hh

Dd

H h

Dd


active component

D

L

12Х18Н10T steelactive component

12Х18Н10T (-ID) steel 12Х18Н10T (-ID) steel

Notes:All source capsules are argon-arc (TIG) seal welded.Integrity Rating according to the State Standard GOST R 52241 (ISO 2919) is "ISO/99/С65546" for IBN-1 – IBN-8 and IBN-13 – IBN-23, "ISO/99/С64444" for IBN-28, "ISO/99/Е65546" for all the other source codes.The source designs are Special Form certified.The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by: a) vacuum bubble test; pass criterion – no bubbles observed;b) helium pressurisation test; pass limit – 1.0 cm3·Pa·s-1.

Principal Technical SpecificationsDouble encapsulation of an active component in the form of pelletised intermetallic composition of Plutonium Dioxide with Beryllium powder, in corrosion-resistant steel.The designated working life of the sources is 10 years from the date of QC final acceptance for IBN-1 – IBN-27 and 5 years from QC final acceptance for IBN-28.

ApplicationRadioisotope instruments; as measurement reference standards.

IBN Source Series

Source Code


Fast Neutron Output into 4πsr,

s-1


Diameter,D (d)

Height(Length)H (h), (L)

Bq Ci

1

IBN-1 10 (3) 19 (3) (1.00±0.20)·104 2.5·108 6.8·10-3

IBN-2 12 (4) 22 (4) (2.00±0.40)·104 5.0·108 1.4·10-2

IBN-3 12 (5) 22 (5) (5.00±1.00)·104 1.3·109 3.5·10-2

IBN-4 15 (6) 24 (6) (1.00±0.20)·105 2.5·109 6.8·10-2

IBN-5 15 (8) 26 (8) (2.00±0.40)·105 5.0·109 1.4·10-1

IBN-6 18 (10) 28 (10) (5.00±1.00)·105 1.3·1010 3.5·10-1

Pu239 neutron emission


IBN Source Series

Source Code



s-1


Diameter,D (d)

Height(Length)H (h), (L)

Bq Ci

1

IBN-7 21 (13) 31 (13) (1.00±0.20)·106 2.5·1010 6.8·10-1

IBN-8 24 (16) 36 (16) (2.00±0.40)·106 5.0·1010 1.4IBN-9 29 (21) 39 (21) (5.00±1.00)·106 1.3·1011 3.5IBN-10 35 (27) 45 (27) (1.00±0.20)·107 2.5·1011 6.8IBN-11 42 (34) 52 (34) (2.00±0.40)·107 5.0·1011 1.4·101

IBN-12 54 (46) 64 (46) (5.00±1.00)·107 1.3·1012 35

2

IBN-1310 (2) 13 (2)

(1.00±0.20)·103 2.5·107 6.8·10-4

IBN-14 (2.00±0.40)·103 5.0·107 1.4·10-3

IBN-1510 (3) 13 (3)

(5.00±1.00)·103 1.3·108 3.5·10-3

IBN-16 (1.00±0.25)·104 2.5·108 6.8·10-3

IBN-17 12 (4) 16 (4) (2.00±0.50)·104 5.0·108 1.4·10-2

IBN-18 12 (5) 16 (5) (5.00±1.25)·104 1.2·109 3.2·10-2

IBN-19 15 (6) 18 (6) (1.00±0.25)·105 2.5·109 6.8·10-2

IBN-20 15 (8) 20 (8) (2.00±0.50)·105 5.0·109 1.4·10-1

IBN-21 18 (10) 22 (10) (5.00±1.25)·105 1.2·1010 3.2·10-1

IBN-22 21 (13) 25 (13) (1.00±0.25)·106 2.5·1010 6.8·10-1

IBN-23 24 (16) 30 (16) (2.00±0.50)·106 5.0·1010 1.4IBN-24 29 (21) 33 (21) (5.00±1.25)·106 1.2·1011 3.2IBN-25 35 (27) 39 (27) (1.00±0.25)·107 2.5·1011 6.8IBN-26 42 (34) 46 (34) (2.00±0.50)·107 5.0·1011 1.4·101

IBN-27 54 (46) 58 (46) (5.00±1.25)·107 1.2·1012 3.2·101

3 IBN-28 3.2 –(30) (1.20±0.25)·104 2.9·108 7.8·10-3



1. IBN-8-1 – IBN-8-8 Sources

H h

Dd



active component

H h



active component

Dd

Notes:Integrity Rating according to the State Standard GOST R 52241 (ISO 2919) is "ISO/99/С65546" for IBN-8-1 – IBN-8-3, "ISO/99/С65545" for IBN-8-156, "ISO/99/Е65545" for IBN-8-157 and IBN 8 556, "ISO/99/Е65546" for all the other sources codes.The source designs are Special Form certified.The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by: a) vacuum bubble test; pass criterion – no bubbles observed;b) helium pressurisation test; pass limit – 1.0 cm3·Pa·s-1.

Principal Technical SpecificationsDouble encapsulation of an active component in the form of pelletised intermetallic composition of Plutonium Dioxide (Plutonium-238) with Beryllium powder, in corrosion-resistant steel. Inner and outer capsules are argon-arc (TIG) seal welded.The designated working life of the sources is 10 years from the date of QC final acceptance for IBN-8-1 - IBN-8-6 and 5 years from the date of QC final acceptance for IBN-8-7 - IBN-8-9, IBN-8-156, IBN-8-157, IBN-8-556.

ApplicationRadioisotope instruments for analysis of rock and bulk materials, automatic remote moisture content gauging in ore dressing

IBN-8-1 – IBN-8-9 Source Series

Source Code



s-1


Diameter,D (d)

HeightH (h) Bq Ci

1

IBN-8-1 10 (4) 13 (4.2) (5.00±1.00)·105 1.2·109 3.2·10-1

IBN-8-2 12 (5) 16 (5.2) (1.00±0.20)·106 2.4·1010 6.5·10-1

IBN-8-3 15 (6) 18 (6.2) (2.00±0.40)·106 4.8·1010 1.3

IBN-8-4 15 (8) 20 (8.2) (5.00±1.00)·106 1.2·1011 3.2

IBN-8-5 18 (10) 22 (10.2) (1.00±0.20)·107 2.4·1011 6.5

IBN-8-6 21 (13) 25 (13.5) (2.00±0.40)·107 4.8·1011 13

IBN-8-7 19.5 (12.3) 40 (30)

(5,00±1,00)·107 1.2·1012 32IBN-8-8 24 (17) 30 (17)

2

IBN-8-9 30 (22) 24 (10)

IBN-8-156

10 (6.9)

10 (7) (1,50±0,50)·106 2.4·1010 6.5·10-1

IBN-8-556 20 (17) (5,50±0,50)·106 12.4·1010 3.3

IBN-8-157 35 (32) (1,50±0,50)·107 4.8·1011 13


2. IBN-8-9, IBN-8-156, IBN-8-157, IBN-8-556 Sources


4. IBN-241 Source Series*3. IBN-241 Source Series*

2. IBN-241 Source Series*1. IBN-241 Source Series*

H h

Dd

H

D

Hh

Dd

h

Hh

Dd

12Х18Н10T steel**

12Х18Н10T steel** 12Х18Н10T steel**

12Х18Н10T steel**

12Х18Н10T steel**

12Х18Н10T steel** 12Х18Н10T steel**

12Х18Н10T steel**

active component

active component active component

active component

Notes:Inner and outer capsules are argon-arc (TIG) seal welded.Integrity Rating according to the State Standard GOST R 52241 (ISO 2919) is "ISO/99/Е65546" for IBN-241-6 – IBN-241-9, IBN-241-В, IBN-241-К, IBN-241-16-1, IBN-241-17-1 – IBN-241-17-3, IBN-241-19-1 and IBN-241-19-2, and "ISO/99/С65546" for all the other sources codes.The source designs are Special Form certified.The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by: a) vacuum bubble test; pass criterion – no bubbles observed;b) helium pressurisation test; pass limit – 1.0 cm3·Pa·s-1.

*Refer to the Specifications Table below for the relevant Figure number.

Principal Technical SpecificationsDouble encapsulation of an active component in the form of pelletised intermetallic composition of Americium Dioxide (Americium-241) with Beryllium powder, in corrosion-resistant steel.The designated working life of the sources is 10 years from the date of QC final acceptance.

ApplicationRadioisotope instruments.

Am241 neutron emission


IBN-241 Source Series

Source Code

Dimensions of the Source (Active Component), mm Fast Neutron

Output into 4πsr,s-1


Diameter,D (d)

HeightH (h) Bq Ci

1

IBN-241-1-1 10 (3) 13 (3) (1.00±0.20)·105 2.40·109 6.50·10-2

IBN-241-2-1 12 (4) 16 (4) (2.00±0.40)·105 4.80·109 1.29·10-1

IBN-241-2-2 12 (5) 16 (5) (5.00±1.00)·105 1.20·1010 3.30·10-1

IBN-241-4-1 15 (6) 18 (6) (1.00±0.20)·106 2.40·1010 6.50·10-1

IBN-241-5-1 15 (8) 20 (8) (2.00±0.40)·106 4.80·1010 1.29

IBN-241-6-1 18 (10) 22 (10) (5.00±1.00)·106 1.20·1011 3.30

IBN-241-7-1 21 (13) 25 (13) (1.00±0.20)·107 2.40·1011 6.50

IBN-241-В-1

25 (17) 46 (36)

(5.60±0.56)·106 1.20·1011 3.30

IBN-241-В-2 (9.3±0.9)·106 2.00·1011 5.50

IBN-241-В-3 (1.10±0.11)·107 2.40·1011 6.60

IBN-241-В1-1 35 (27) 45 (27) (1.10±0.11)·107 2.40·1011 6.60

2IBN-241-К-1

50.5 56.5(1.70±0.50)·107 4.40·1011 1.20·101

IBN-241-К-2 (4.00±0.70)·107 9.60·1011 2.60·101

1

IBN-241-8-1 24 (16) 30 (16) (2.00±0.40)·107 4.80·1011 1.29·101

IBN-241-9-1 29 (21) 33 (21) (5.00±1.00)·107 1.20·1012 3.30·101

IBN-241-10-1

7.844max (4.4) 10.00max (4.6)

(2.60±0.26)·104 5.55·108 1.50·10-2

IBN-241-10-2 (7.50±0.75)·104 1.60·109 4.32·10-2

IBN-241-10-3 (9.0±0.9)·104 1.90·109 5.14·10-2

IBN-241-11-19.070max (5.2) 12.80max (4.8)

(1.10±0.09)·105 2.30·109 6.22·10-2

IBN-241-11-2 (2.20±0.18)·105 4.80·109 1.30·10-1

3IBN-241-12-1

12.740max (9.2) 13.20max (7.4)(2.45±0.20)·105 5.18·109 1.40·10-1

IBN-241-12-2 (4.40±0.35)·105 9.50·109 2.56·10-1

1

IBN-241-13-1 14.350max (11.3) 31.75max (25.0) (6.50±0.52)·106 1.40·1011 3.78

IBN-241-14-1

17.475maх (13.9) 19.40max (11.9)

(2.20±0.18)·103 4.80·107 1.30·10-3

IBN-241-14-2 (6.60±0.53)·103 1.40·108 3.78·10-3

IBN-241-14-3 (2.20±0.18)·104 4.80·108 1.30·10-2

IBN-241-14-4 (6.60±0.53)·104 1.40·109 3.78·10-2

IBN-241-14-5 (2.20±0.18)·105 4.80·109 1.30·10-1



IBN-241 Source Series (continued)

Source Code

Dimensions of the Source (Active Component), mm Fast Neutron

Output into 4πsr,s-1


Diameter,D (d)

HeightH (h) Bq Ci

1

IBN-241-14-6

17.475maх (13.9) 19.40max (11.9)

(6,60±0,53)·105 1,40·1010 3,78·10-1

IBN-241-14-7 (1.00±0.08)·106 2.10·1010 5.68·10-1

IBN-241-14-8 (2.00±0.16)·106 4.30·1010 1.16

4

IBN-241-15-1

22.475maх (17.4)31.20max (17.7)

(2.20±0.18)·104 4.80·108 1.30·10-2

IBN-241-15-2 (4.40±0.35)·105 9.50·109 2.57·10-1

IBN-241-15-3 (1.10±0.08)·106 2.30·1010 6.22·10-1

IBN-241-15-4 (2.20±0.18)·106 4.80·1010 1.30

IBN-241-15-5 (2.45±0.20)·106 5.20·1010 1.40

IBN-241-16-1 48.60max (35.1) (6.60±0.53)·106 1.40·1011 3.78

IBN-241-17-1

30.131max (25.1) 60.20max(46.6)

(1.10±0.08)·107 2.30·1011 6.22

IBN-241-17-2 (2.20±0.15)·107 4.44·1011 12.00

IBN-241-17-3 (3.00±0.24)·107 6.30·1011 17.00

1

IBN-241-18-1

7.920max (4.4) 15.20max (9.0)

(2.20±0.18)·104 4.80·108 1.30·10-2

IBN-241-18-2 (6.60±0.46)·104 1.40·109 3.78·10-2

IBN-241-18-3 (1.10±0.08)·105 2.30·109 6.22·10-2

IBN-241-18-4 (1.75±0.14)·105 3.70·109 1.00·10-1

IBN-241-18-5 (2.20±0.18)·105 4.80·109 1.30·10-1

4ИБН-241-19-1

49.255max (41.0) 81.15max (70.0)(5.00±0.35)·107 1.00·1012 27.03

ИБН-241-19-2 (1.00±0.07)·108 2.10·1012 56.76

Notes:**Material of the source outer and inner capsules:– 12Х18Н10Т or 12Х18Н10Т-ID steel (equivalent to 300 series steel) for IBN-241-1 – IBN-241-9, IBN-241-В, IBN-241-К source designs;– 02Х17Н14М2-ID (-IDD) steel (equivalent to 316L steel) for IBN-241-10 – IBN-241-12, IBN-241-14 – IBN-241-19 source designs;– ХН65МВ alloy for IBN-241-13 source design.



1. М41Н72-45, М41Н72-71 Sources

Notes:Capsules are argon-arc (TIG) seal welded.Integrity Rating of М41Н72-45, М41Н72-71 sources is "ISO/99/Е64444" according to the State Standard GOST R 52241 (ISO 2919).The source designs are Special Form certified.The sources are leak tested according to the State Standard GOST R 51919 (ISO 9978) by: a) vacuum bubble test; pass criterion – no bubbles observed;b)helium pressurisation test; pass limit – 1.0 cm3·Pa·s-1.

Principal Technical SpecificationsSingle encapsulation of an active component in the form of pelletised intermetallic composition of Americium Dioxide (Americium-241) with Beryllium powder, in corrosion-resistant steel.The designated working life of the sources is 15 years from the date of QC final acceptance.



Source Code

Dimensions of the Source, mmFast Neutron Output

into 4πsr,s-1


Diameter,D

HeightH Bq Ci

М41Н72-4520.0+0.0 80.0+0.0 не менее 3.60·107 6.66·1011 1.8∙101

М41Н72-71–0.1 –0.3

H

D

steel 02Х17Н14М2-ID, 02Х17Н14М2-IDD) for domestic

market

active component

steel to ISO 5832-1 for export


1. IRIPL Source Series

H

Dd

08 kp steel

aluminium alloy, grade AB

active component

Notes:The sources are sealed with epoxy glue.Integrity Rating of the sources is "ISO/99/С34344" according to the State Standard GOST R 52241 (ISO 2919).The sources are leak tested by vacuum bubble test according to the State Standard GOST R 51919 (ISO 9978); pass criterion – no bubbles observed.

Principal Technical SpecificationsHolder comprising a lid and a body with an enamelled insert that incorporates Plutonium-238 activity deposited on the working surface of the insert.The designated working life of the sources is 5 years from the date of QC final acceptance.


IRIPL Source Series

Source Code


Photon Flux Density at a Distance 1 m from the Working Window

Centre, s-1·cm-2

Maximum Pu238 Content Activity in a Source

Diameter,D (d)

Height,H (h) Bq Ci

IRIPL-1

12 (7) 10

(2.5±0.80)∙102 6.6∙108 17.8

IRIPL-2 (5.0±1.5)∙102 1.3∙109 35.1

IRIPL-3 (1.00±0.30)∙103 2.6∙109 70.2

Pu238 X-ray emission


1. IRIZh Source Series

H

Dd

copper or copper alloys

Notes:The sources are sealed either with nickel and glue films, or glue.Integrity Rating of the sources is "ISO/99/С33222" according to the State Standard GOST R 52241 (ISO 2919).The sources are leak tested by a dry wipe test according to the State Standard GOST R 51919 (ISO 9978); pass limit – 185 Bq.

Principal Technical SpecificationsBacking plate with Iron-55 deposit on its working window.The designated working life of the sources is 3 years from the date of QC final acceptance.


IRIZh Source Series

Source Code


Photon Flux Density at a Distance 1 m from the

Working Window Centre, s-1·cm-2

Maximum Fe55 Content Activity in a Source

Diameter,D (d)

Height,H (h) Bq Ci

IRIZh-1

14 (10) 1

(6.0 )∙101 1.4∙108 3.8∙10-3

IRIZh-2 (3.00 )∙102 7.1∙108 1.9∙10-2

IRIZh-3 (1.50 )∙103 3.5∙109 9.4∙10-2

Fe55 X-ray emission

+4.2–2.4

+2.10–1.20

+1.05–0.60

active component


12Х18Н10Т(-ID) steel

Principal Technical SpecificationsActive component with Stronium-90+Yttrium-90 encapsulated in capsules.The designated working life of the sources is 5 years from the date of QC final acceptance.


Notes:The source capsules are argon-arc (TIG) seal welded.Integrity Rating of the sources is С 55546 according to the State Standard GOST 25926 (ISO 2919).The sources are leak tested by immersion test according to the State Standard GOST R 51919 (ISO 9978); pass limit – 200 Bq.

1. IRIS Source Series

Hh

Dd

titanium or titanium alloys

active component

aluminium or aluminium alloys

IRIS Source Series

Source Code


Exposure Dose Rate at a Distance 1 m from the

Centre of the Source Working Window ,

A/kg

Maximum Sr90+Y90 Content Activity in a Source

Diameter,D (d)

Height,H (h) Bq Ci

IRIS-1

14.2 (9) 17.6

(5.2 )∙10-10 5.5∙1010 1.5

IRIS-2 (2.30 )∙10-9 2.5∙1011 6.8

IRIS-3 (1.20 )∙10-8 1.2∙1012 32.4

Sr90+

Y90 X-ray emission

+3.6–2.1

+1.6–0.92

+0.84–0.48


1. IRIP Source Series

Hh

Dd

aluminium alloy

active component

aluminium alloy

Principal Technical Specifications:Active component with Promethium-147 encapsulated in capsules.The designated working life of the sources is 5 years from the date of QC final acceptance.

Application:Radioisotope instruments

Notes:The sources are sealed with glue.Integrity Rating of the sources is С 34445 according to the State Standard GOST 25926 (ISO 2919).The sources are leak tested by immersion test according to the State Standard GOST R 51919 (ISO 9978); pass limit – 200 Bq.

IRIP Source Series

Source Code

Dimensions of the Source (Working Window), mm Photon Flux Density of 3.2-9.6 fJ

X-Ray Emission at a Distance 1 m from the Working Window Centre,

s-1·cm-2

Maximum Pm147 Content Activity in a Source

Diameter,D (d)

Height,H Bq Ci

IRIP-1

10 (5.9) 14

(1.20 )∙102 2.4∙1010 6.5∙10-1

IRIP-2 (6.0 )∙102 1.2∙1011 3.2

IRIP-3 (3.00 )∙103 5.9∙1011 15.9

IRIP-4 (8.0 )∙103 1.6∙1012 43.2

Pm147 X-ray emission

+5,6–3,2

+2.10–1.20

+4.2–2.4

+0.84–0.48


1. IRIT Source Series

H

Dd

aluminium alloy

active component

Notes:The sources are sealed with glue.Integrity Rating of the sources is С 34445 according to the State Standard GOST 25926 (ISO 2919).The sources are leak tested by immersion test according to the State Standard GOST R 51919 (ISO 9978); pass limit – 200 Bq.

Principal Technical Specifications:Active component as neutron-irradiated discs of lead-thallium alloy encapsulated in capsules.The designated working life of the sources is 5 years from the date of QC final acceptance.


IRIT Source Series

Source Code


mm Photon Flux Density of 7.2-15.2 fJ X-Ray Emission at a Distance 1 m

from the Working Window Centre, s-1·cm-2

Maximum Tl204 Content Activity in a Source

Diameter,D (d)

Height,H Bq Ci

IRIT-1

15.5 (10) 8.5

3.00 3.8∙107 1.0∙10-3

IRIT-2 (1.20 )∙102 1.5∙109 4.1∙10-2

IRIT-3 (6.0 )∙102 7.5∙109 2.0∙10-1

IRIT-4 (3.00 )∙103 3.8∙1010 1.0

Tl204 X-ray emission

+2.1–1.2

+0.84–0.48

+4.2–2.4

+2.10–1.20


Note: Bulk isotope is rated subject to the content activity of Americium-241 in the capsule referenced to the despatch date plus Americium-241 content activity at the date of activity evaluation for export deliveries.

* Bulk isotope specifications correspond to the relevant parameter values referenced to the despatch date.** Bulk isotope specifications correspond to the relevant parameter values referenced to their measurement date.

Principal Technical SpecificationsAmericium-241 in americium dioxide powder form (hereinafter “the bulk isotope” or the “product”) is supplied in capsules seal welded by argon-arc (TIG) welding.Americium-241 mass in the capsules does not exceed 9.00, 36.00 and 90.00 g (subject to the capsule used).

Application:Grade A - to manufacture ionising sources, etc.Grade B - to manufacture fast neutron sourcesGrade V - as targets for reactor irradiations yielding transamericium nuclides

SpecificationsValue

Grade A Grade B Grade V

1* Mass fraction of Americium-241 in the product, %, not less than 82.0 62.0 52.0

2** Mass fraction of Americium-243 relative to Americium-241 mass, %, not more than - 30.0 30.0

3** Mass fraction of Curium-244 relative to Americium-241 mass in the product, %, not more than - 4.0 30.0

4** Mass fractions of Boron, Cadmium, Gadolinium relative to Americium-241 mass, %, not more than - - 0.3

5**Cumulative notional percentage of gamma-emitting impurities by activity (ratio of total activity of gamma-emitting impurities to Americium 241 activity) in the product in the range of measured energy more than 60 keV, %, not more than

- 5·10-2 5·10-2

6* Specific activity of Americium-241 in the product, Bq/g (Ci/g) not limited

Am241 bulk isotopes


Note: Bulk isotope is rated subject to the content activity of Plutonium-238 in the capsule referenced to the despatch date plus Plutonium-238 content activity at the date of activity evaluation for export deliveries.

* Bulk isotope specifications correspond to the relevant parameter values referenced to the despatch date, ** Bulk isotope specifications correspond to the relevant parameter values referenced to their measurement date.

Principal Technical Specifications:Plutonium -238 in the plutonium dioxide powder form (hereinafter “the bulk isotope” or the “product”) is supplied in capsules seal welded by argon-arc (TIG) welding.Plutonium-238 mass in the capsules does not exceed 40.00, 80.00 and 180.00 g (subject to the capsule used).

Application:Raw Material:Grade A - for heat and ionising sources;Grade B - for biomedical sources.

SpecificationsValue

Grade A Grade B

1* Mass fraction of Plutonium-238 in the product, %, not less than 67.0 59.0

2*

Mass fraction of the isotopes, %:- Plutonium-238, not less than 80.00 70.00

- Plutonium-239+Plutonium-240+Plutonium-241+Plutonium-242, not more thanrelative to the total of the mass fractions of Plutonium isotopes 20.00 30.0

3** Total mass fraction of Plutonium isotope dioxides (Plutonium 238+Plutonium 239+Plutonium 240+Plutonium 241+Plutonium 242) in the product, %, not less than 95.0 95.0

4** Mass fraction of Plutonium-236 relative to Plutonium-238 mass, %, not more than 2.0·10-4 3.0·10-5

5** Neutron flux rate from Plutonium-238, s-1· g-1, not more than 2.5·104 1.9·104

6 Exposure dose rate of gamma emission at a distance 1 m from the product containing 1 g of Plutonium-238, A·kg-1, not more than 8·10-11 3·10-11

7** Cumulative content of gamma-emitting impurities relative to Plutonium-238 content by activity, %, not more than 2.0·10-4 1·10-4

8* Specific activity of Plutonium-238 in the product, Bq/g (Ci/g) not limited

Pu238 bulk isotopes


Principal Technical Specifications:Helium-3 gas can be supplied in:- 0.8-litre cylinders under pressure up to 8.83 MPa;- 5-litre and 10 litre cylinders under pressure up to 14.71 MPa.

Application:Cryogenic equipment, neutron detectors, laser instruments, magnetic-resonance tomography, spectroscopy, non destruc-tive testing, thermonuclear fusion process control.

SpecificationsValue

High

Category

First

CategoryFirst Grade

Sort A Sort B

1 Atomic fraction of Не3,%, not less than 99.990 99.950 99.800 99.600

2 Atomic fraction of Не4, %, not more than 0.010 0.050 0.200 0.400

3 Total helium volume fraction (Не3+Не4), %, not less than 99.995

4 Nitrogen volume fraction, %, not more than 6∙10-4

5 Volume fraction of Oxygen and Argon in sum, %, not more than 6∙10-4

6 Volume fraction of Hydrocarbons, %, not more than 6∙10-4

7 Hydrogen volume fraction, %, not more than 6∙10-4

8 Volume fraction of Carbon Oxide, %, not more than 6∙10-4

9 Atomic fraction of Tritium, %, not more than 1∙10-11

10 Volumetric activity of Tritium, Bq/l (Ci/l), not more than 4.8 (1.3∙10-10)

He3 bulk isotopes


Principal Technical Specifications:Krypton-85 gas can be supplied either in manufacturer’s or in customer’s containers. Unenriched krypton with the volume fraction of Krypton-85 4.0 to 7.0 % and enriched Krypton with the volume fraction of Krypton-85 10.0 to 50.0 % of the sum of all krypton isotopes, are available for supplies.

Application:Non-destructive testing, as a radioactive tracer in gases, in gas-discharge devices, in beta-source manufacture.

Specifications Values

1 Total volume fraction of chemical impurities (Hydrogen, Helium, Nitrogen, Oxygen+Argon*, Xenon), %, not more than 1.00

2Radioactive impurities content by activity, %, not more than:

- Xenon-133 content by activity- other gamma-emitting impurities content by activity

0.1

Kr85 bulk isotopes

* Recognised as one impurity


Note: Bulk isotope is rated subject to Carbon-14 activity, percentage of radioactive impurities content by activity and content of chemical impurities referenced to the date of evaluation.

Principal Technical Specifications:Carbon-14 is supplied in glass C-2 ampoules (capacity up to 2 cm3) or C-5 ampoules (capacity up to 4 cm3), wrapped in aluminium foil and placed in an ampoule, as well as in 20 cm3 and 50 cm3 ampoules placed in a can.

Application:As feed material in manufacture of labelled compounds.

Specifications

Value

Grade

“technical”

Grade “ch” (“pure”) Type “V”

Grade “ch” (“pure”) Type “B”

Grade “ch” (“pure”) Type “A”

1 Mass fraction of Carbon-14, %, not less than 97.0

2 Mass fraction of chemical impurities in the product, %, not more than 2.90

3 Specific activity of Carbon-14 in the product, Bq/g (mCi/g)

from 8.88∙109

to 9.95∙109

(240 to 269)

> 9.95∙109 to 10.36∙109

(269 to 280)

> 10.36∙109

to 10.73∙109

(280 to 290)> 10.73∙109

(> 290)

4 Activity of Carbon-14 in an ampoule, Bq (Ci)

≤ 1.036∙1010

(≤ 0.280)> 1.04∙1010

to 10.36∙1010

(> 0.28 to 2.80)> 10.36∙1010

(> 2.80)

5 Percentage of radioactive impurities content by activity, %, not more than 1∙10-2

C14 bulk isotopes


Note: Bulk isotope is rated subject to activity and specific activity of Strontium-90 referenced to the despatch date, percentage of radioactive impurities content by activity at the date of evaluation.

Principal Technical Specifications:Strontium carbonate is supplied in sealed capsules complying with Special Form Material requirements.

Application:Intended for domestic market and export supplies, and for use as a raw material in ionising sources manufacture.

Specifications Values

1 Strontium-90 specific activity in the product, GBq/g (Ci/g), not less than 8.14∙102 (22.0)

2 Yttrium-90 content by activity, %, not more than in equilibrium

3

Percentage of radioactive impurities content by activity, %, not morethan:- Strontium-89- Cerium-144+Praseodymium-144- other gamma-emitters

1.00.200.50

Sr90 bulk isotopes


NOTES


ROSATOM STATE ATOMIC ENERGY CORPORATION FEDERAL STATE UNITARY ENTERPRISEMAYAK PRODUCTION ASSOCIATION

CONTACT DETAILS31, Lenin St., Ozyorsk, Chelyabinsk Region,Russia 456780Tel.: (351-30) 3-70-11, 3-31-05Fax: (351-30) 3-38-26

e-mail: [email protected] [email protected]

[email protected] mayak” pa · 2017-12-20 · (automatic smoke detectors in fire alarm...

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