joint stock company “afrikantov okb mechanical engineering ... · 4 5 artesian pumps and...

SERVING THE NUCLEAR MACHINEBUILDING INDUSTRY SINCE 1945

JSC “Afrikantov OKBM”

JSC “Afrikantov OKBM”Burnakovsky proezd, 15, Nizhny Novgorod, 603074 Russia

Tel.: +7 (831) 275-40-76, 275-26-40Fax: +7 (831) 241-87-72

[email protected]

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Joint Stock Company “Afrikantov OKB Mechanical Engineering”

Equipmentfor Nuclear Power Plants

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1

Main Circulation Pumps for Sodium- and Water-Cooled RPs

The pumps are designed to provide coolant circula-tion in the primary and secondary systems of BN–800 RPs and other fast RPs, as well as in the circuit of the RBMK–1000 channel reactor.

At present MCP-1 and MCP-2 of RP BN-800 are suc-cessfully operated at Beloyarskaya NPP.

TsVN-8 RBMK-1000 RP MCP

CEFR RPMCP-1

CEFR RPMCP-2

BN-600 RP MCP-1

High quality of MCPs devel-oped by JSC “Afrikantov OKBM” has been proved by more than 35 years of operation within the BOR–60, BN–350, BN–600, and RBMK–1000 RPs.

PUMP EQUIPMENT AND VALVES

BN-800 RP MCP-2 BN-800 RP MCP-1

MCP-1 MCP-2

Capacity, m3/h 12,300 11,500

Head, m 101 48

Pumped medium temperature, °С 354 309

Electric motor power, kW 5,000 2,500

2 3

ATsNSB 150-110 Emergency Boron Injection Pump

The pump is designed to inject boric acid solution from the emergency storage tank into the primary system of VVER-1000 NPPs in emergency modes associated with primary system cooldown. The safety class is 2.

Nominal capacity, m3/h 150

Nominal head, m 980

Working temperature at the pump inlet, °С 10–95

Power in the nominal mode (at pumped medium density of 1,020 kg/m3), kW, not more than— pump power— unit power

685715


Nominal head, m 885

Температура на входе в насос рабочая, °С 20–60


620650

TsNR 800-230Т Emergency Cooling Down Pump

The pump is designed to inject boric acid solution into the primary system of VVER-1000 NPPs to remove heat from core under normal/abnormal operation conditions and in emergency modes. The safety class is 2.


Nominal head, m 230



635665

ATsNSB 150-90 Emergency Feedwater Pump

The pump is intended to deliver desalinated water to steam generators in the abnormal operation modes and emergency modes at VVER-1000 NPPs. The safety class is 2.

Safety System Pumps for VVER-1000 RPs

ATsNSB 150-90G Auxiliary Feedwater Pump

The pump is intended to supply feedwater to steam generators in the startup and shutdown modes of the unit, as well as at loss of power of the VVER–1000 NPP unit. The safety class is 3.


Nominal head, m 910


Power in the nominal mode (at pumped medium density of 897.5 kg/m3), kW, not more than

587

ЦНР 800-230Р

ЦНСА 700-140Р

Capacity, m3/h 800 700

Head, m 230 140

Pumped medium temperature, °С 150 150

Electric motor power, kW 800 500

The pumps are designed to operate within the emer-gency and scheduled cooling down system, as well as the spray system of the VVER-1000 power unit. The pumps are safety class 2.

4 5

Artesian Pumps and Semi-Submersible Pumps

The pumps are designed to deliver process water to NPP cooling systems.

TsVA 1350-35 TsVA 20-30

Capacity, m3/h 20–2,900

Head, m 16–67

Pumped medium temperature, °С 5–35

Electric motor power, kW 7.5–500

Pumping Equipment Test Facilities

JSC “Afrikantov OKBM” has a test facility base to carry out full-scale tests of BN-800 RP MCP-1/MCP-2 and virtually all the pumping equipment of NPP systems.

Twenty-three pump dimension types have been to date developed and are being now manufactured.

Facility for testing pumps of 200–1,200 m3/h

Submersible Pumps

TsPN 25/20 electric pump TsPN 2/25 electric pump GEN 16/30 canned electric pump

TsPN 25/20 TsPN 2/25 TsPN 2/50 GEN 16/30

Capacity, m3/h 25 2 2 16

Head, m 20 25 50 30

Pumped medium temperature, °С 60 60 60 60

Submersion depth, m 20 3 3 1

Electric pump power, kW 4 2.1 2.9 5

Electrical pump mass, kg, not more than 120 78 88 260


Nominal head, m 140



365385

TsNSA 700-140T Spray Pump

The pump is designed to provide injection of solution from the spay solution storage tank into the contain-ment air space to reduce pressure and temperature of the accident location area and to bind radioactive iodine available in the vapor and air of the pressur-ized volume in design basis emergency modes at VVER–1000 NPPs. The safety class is 2.

6 7

Pump Shaft End Seals

Shaft end seals are developed and manufactured for a wide range of pumps. End seals are intended to seal pump shafts at minimal leaks of the pumped medium in all operation modes.

All the pumps developed by JSC “Afrikantov OKBM” are equipped with these seals. End seals are delivered for the pumps in the current NPPs.

Air Intake Shut Down Valve

The air intake shut down valve in NPP 2006 is de-signed to protect turbine condensers and main cool-ing water system pipelines from hydraulic impacts at emergency trip of hydraulic circulation pump units and from air discharge when main system pipelines and condenser pipelines are filled with cooling water. The safety class is 4.

Shaft diameter, mm 28–450

Shaft rotation speed, rpm 600–3,500

Seal leak, l/h, not more than 5

Facility for testing MCP-1/MCP-2 for the BN-800 RP

Facility for testing Artesian pumps of 120–3,500 m3/h

Facility for testing pumps of 500–4,500 m3/h Facility for testing pumps of 20–250 m3/h

8 9

Non-return shutoff pneumatic valve, shutoff pneumatic valves are designed for operation as shutoff device for the primary and secondary circuit pipes.

Pneumatic gate valve is designed for operation as shutoff device for the secondary circuit steam pipes.

Pneumatic ball valve DN180 is designed for operation as shutoff device for the secondary circuit pipes.

Stop and non-return-stop valves

The valves designed for high parameters of working medium, belonging to equipment group “B” as per PNAE G-7-008-89, valve grade and group “2ВIIa” as per NP-068-05, and safety grade 2 as per classification NP-022-2000 (class identification 2NZL).

Working medium water, steam, water-steam mixture

Design pressure, MPa 17.7

Design temperature, °С 350

Pressure drop of the working medium at the opening, not more than MPa

9.8

Leak tight class of the gate as per GOST 9544-2015— valves — gate valves, ball valve

В С

Valve DN65 Gate valve DN150Valve DN 80 Ball valve DN180

Nominal diameter 400

Working mediumrecirculated

sea water, air

Working medium temperature, °С, not more than 43

Working pressure, MPa (kgf/cm2), not more than 0.36 (3.7)

Valve air flow-rate, m3/s, not more than 5.0

Calculated temperature, °С 50

Hydraulic testing pressure, MPa (kgf/cm2), not more than 0.6 (6.1)

Three-Way Switching Device

The three-way switching device is intended to switch alternately the channels for gas medium discharge from the SAS-2 second-stage emergency discharge vessel of the emergency protection system in the BN-800 RP SG. The safety class is 3.

Nominal diameter 50

Calculated pressure, MPa (kgf/cm2) 0.7 (7.14)

Calculated temperature, °С 300

Working medium

— temperature, °С, not more than— medium pressure, MPa (kgf/ cm2), not more than

Argon as per GOST 10157, sodium vapor, hydrogen

NaOH, Na₂O45

0.0078 (0.08)

10 11

Air Heat Exchanger of the Emergency Cooling Down System for the BN-800 RP in Beloyarsk NPP Unit 4

The air heat exchanger (AHX) is designed to transfer heat from ECDS intermediate system cool-ant to atmospheric air.

Thermal power, MW, not less than 13

Sodium inlet temperature, °С 505

Air inlet temperature, °Сminus 44

to plus 39

Calculated sodium pressure at calculated temperature, MPa, not more than

1

AHX mass not more than, t 35

Materials used 08Cr18Ni10Ti steel

Safety class 3

Working medium— cooling medium (in-tube space)

— medium being cooled (inter-tube space)

water,steam-water mixture

steam-gas mixture

Maximal thermal power, MW 1.33

Calculated parameters— temperature, °С— pressure, MPa

1900.7

Mass, kg (in the dry condition) 4,340


Safety class 3

Working medium— medium being cooled (in-tube space)— cooling medium(inter-tube space)

steam, condensate

water

Maximal thermal power, MW 3.25

Calculated parameters ofthe medium being cooled— temperature, °С— pressure, MPa

3008.1

Calculated parameters ofthe cooling medium— temperature, °С— pressure, MPa

1150.13

Calculated mass in the dry condition, kg

950


Safety class 3

Heat Exchanger of the Passive Heat Removal System for the NPP 2006 Containment

The heat exchanger operates within the system of passive heat removal from containment.

Heat exchange of the passive heat removal system through NPP 2006 steam generators

The heat exchangers operate within the system for passive heat removal through steam genera-tors. The system pertains to technical means for coping with beyond-design-basis accidents.

HEAT EXCHANGE EQUIPMENT

12 13

Heat exchanger ‘Water — Water’

Type of the heat exchanger — surface, tube, shell-and-tube heat exchanger. Heat ex-changing surface is made of straight tubes. The flow of the cooling and cooled water is counterflow-crosswise.

Working medium— cooling (tube side)— cooled (shell side)

water distilled water

Design parameters— temperature (maximum), °C— pressure, MPa

500.98

Dry weight, tons 20/35

Materials used alloy 08Cr18Ni10Ti

Piping system of heat exchanger ‘Water — Water’

Working medium— cooling (tube side)— cooled (shell side)

waterair

Design parameters— temperature (maximum), °C— pressure (maximum), MPa

3500.6

Dry weight, tons 10

Materials used alloy 08Cr18Ni10Ti

Heat exchanger ‘Gas — Water’

Type of the heat exchanger — surface, tube, shell-and-tube heat exchanger.The tube system is implemented with external spiral finning and hight of active part equal to 1100 mm. The tubes are connected with headers in heat exchanging sections with parallel-subsequent connection of tubes in one heat exchanging section. A number of heat exchanging sections, located in a shell, form the heat exchanger module.

14 15

Radial Fans

Capacity (volume flow rate) m3/h 1,000–120,000

Fan total pressure, Pa 160–3,500

Climatic version as per GOST 15150-69 V

Safety class 2, 3, 4

Seismic class as per NP-031-01 1

Stability under impact loads in any direction3g (for the FPU,

UNI*)

Axial Fans

VENTILATION EQUIPMENT Heat Exchanger of the Emergency Cooling Down System for the KLT-40S RP FPU

The heat exchanger of emergency cooling down system (ECDS) is designed to operate within the ECDS passive channel providing heat removal from the steam-generating unit during accidents with long-term loss of power.

Heat exchanger power, kW, not less than 2,200

Working mediumWater, steam, steam-water

mixture

Calculated pressure, MPa— of the pipe system— of the inter-pipe space

16.20.1

Calculated temperature, °С, not more than— at the pipe system inlet— of the inter-pipe space

320106

Calculated mass as delivered, kg 3,550


Safety class 2

*UNI=Universal Nuclear Icebreaker

16 17

Recirculation Cooling Plants

Ventilation Valves

Valves are intended to ensure leak-free shutoff of pipelines at FPU and UNI RPs.

The application area is a containment heat removal system, containment emergency pressure decrease system, and controlled area ventilation system.

Nominal diameter, mm 100–500

Safety class 2, 3, 4

Stability under impact loads in any direction 3g

Capacity (volume flow rate), m3/h 620–35,000



Safety class as per NP-001-97 2NO, ЗNO


Axial and radial fans are intended to circulate air in compartments.

The application area of

radial fans — NPP ventilation systems that are important for safety. axial fans — NPP ventilation systems that are important for safety, FPU ventilation systems,

and UNI ventilation systems.

Capacity (volume flow rate), m3/h 5,300–12,000





Radial explosion-proof fans are designed to transfer steam- and gas-air explosive mixtures.

The radial explosion-proof fans are used in exhaust ventilation systems for accumulator compartments. Exhaust ventilation systems are safety assurance systems and provide normal operation of NPPs. The radial explosion-proof fans are also applied in ex-haust systems of other compartments.

Radial Explosion-Proof Fans

Nominal air capacity, m3/h 2,500–95,000

Nominal cooling capacity, kW 18–650



Recirculation cooling plants are designed to

cool air in NPP building compartments and fulfill NPP safety assurance functions that relate

to creation and maintenance of conditions neces-sary for operation of process systems and safety elements.

18 19

Portable filtering station

Portable filter unit is designed:

to clean air and to remove radioactive and toxic substances on site occurring during operations connected with cutting, welding and scrubbing of equipment contaminated with radioactive nu-clides in the course of repairs in indoor space of the controlled access zone at NPP;

Air Coolers

Air coolers and air cooler units are intended to

remove heat and moisture release from process equipment and to maintain the specified air parameters in NPP compartments,

be used as part of NPP ventilation systems important for safety and of those that do not affect safety, and

fulfill NPP-normal-operation-and-safety-assurance functions that relate to creation and maintenance of conditions necessary for operation of process systems and normal-operation-and-safety elements.

Capacity (volume flow rate), m3/h 2,500–95,000

Nominal cooling capacity, kW 11–700



Ventilation System Protection Devices

Maximum Pressure of Shock Wave Front, kPa 30

Drag Factor, not more 3

Sizes of Flow Path (width×height), mm 250×280÷1000×2000

Safety Class as per NP-001-15 2, 3, 4

Seismic Class as per NP-031-01 1

The devices are designed to protect the ventilation openings of NPP facilities, nuclear fuel cycle facilities or nuclear plants from the air shock wave impact and the deflagration explosion compressive wave.

The scope of application of ventilation system protection devices is as follows: important to safety NPP ventilation systems, including the ventilation systems in a normally occupied area and a controlled access area of the NPP reactor building with artificially controlled climatic conditions, in all macroclimatic areas.

The ventilation system protection devices can be manufactured to feature an additional fixing device ensuring the normal operation of the ventilation system affected by air with a velocity of up to 35 m/s.

to clean air on site with recorded elevated activity or emissions level in indoor space at NPP and other nuclear facilities.

20 21

MPS-V-1000 MPS-V-1200

Mass, kg 48,110 51,000

Mass of articles reloaded

FA (w/o the CPS AR), kg 738 743

CPS AR, kg 18.5 18.5

Leak-tight overpack, kg 472 570

Bridge (transfer mechanism)

Travel speed, mm— minimum— maximum

0.321

0.621

Accuracy of reaching the specified coordinate, mm ±2 ±2

Track, mm 7,300 8,300

Maximum travel, mm 20,800 21,000

Carriage (transfer mechanism)

Travel speed, mm— minimum— maximum

0.312

0.612

Track, mm 3,250 2,650

Accuracy of reaching the specified coordinate, mm ±2 ±2

Maximum travel, mm 5,680 5,820

FA gripper (working beam)

Load-carrying capacity, not more than, kg 23,000 2,345

Deviation from the specified coordinate along the height, mm ±5 ±3

MPS-V-1200 handling machine

Next generation two-channel control sys-tem,

System of monitoring of fuel pin leak tight-ness during reloading of SFA,

CRDMs incorporating AC motors with fre-quency regulation,

The STS-PM-1000 state-of-the-art TV sys-tem to monitor fuel handling,

The STS-PM-1 special TV system to visually monitor handling machine travel,

TV beam with a lifting drive to wind the camera cable, and

A set of the following tools, accessories: – cluster thimble, – device for visual inspection of FA housing, and – device for lifting of a dropped FA.

Production time is not more than 12 months.The assigned lifetime is 30 and 60 years, respectively.After-sales service is provided for equipment.Spare parts are delivered for maintenance repair, mid-life repair, and overhaul.

Handling machines for VVER RPs

Fuel handling machines are intended to carry out handling and process operations to reload fuel in VVER RP cores.

FUEL HANDLING EQUIPMENT

MPS-V-1000 handling machine

22 23

Shim Rod Overpack and Control Rod-Overpack Container

Hydraulic jack working pressure, MPa 46

Force developed by hydraulic jack, kN 60,000

Maximum travel of hydraulic jack pistons, mm 25

Pressure of lowering down the hydraulic jack pistons, MPa 6.0

Number of main joint studs, pcs 24

Number of drives 24

Wrench force to tighten standard nuts, N 100

Overpack overall dimensions, mm— diameter— length

3,277133

Overpack working medium water, air

Overpack water volume (with the installed rod), l 15.2

Overpack water average temperature, °С 60

Overpack gas cavity volume (with the installed rod), not less than

1

Overpack calculated pressure, MPa, not more than 0.09

Overpack test pressure, MPa 0.2 ± 0.01

Empty overpack mass, kg 40.8

KLT-40S Main Joint Nut Unscrewing/Tightening Device

The device provides simultaneous extension of all studs in the reactor main joint. The unscrewing/tightening device makes it possible to automate the extension process and to reduce operation duration. It [device] provides safer operation of joints due to nut uniform tightening.

The overpack is designed to contain and seal spent shim rods in spent fuel pool water.

Fresh Subassembly Transfer Mechanism (FSTM)

The FSTM is designed to remotely load fresh subassemblies (including FAs with mixed uranium-plutonium oxide fuel) into the fresh fuel cask.

AutomatedReloading Complex

The reloading complex is designed to reload nuclear fuel of the KLT-40 S RPs that are located on FPUs and have cassette cores. The complex ensures fuel han-dling, including unloading of spent fuel assemblies (SFA) from the reactor, SFA transfer and placement into cooling and storage tanks. The complex also ensures loading of fresh FAs into the reactor.

Working medium — for separate parts

air (to 30°C)argon (to 100°C)

Load-carrying capacity, kg 300

Gripper working travel, m 6.75

Column working travel along R=2.7 m, m

6.5

Gripper travel speed— basic speed, m/min— creep speed, m/min

5.59 0.4

Column transfer speed along R=2.7 m— basic speed, m/min— creep speed, m/min

8.66 0.62

FSTM overall dimensions— height, m— length, m— width, m

5.834.452.15

FSTM mass, kg 7,500

Assigned lifetime, yrs 45

24 25

Length, mm to 15,000

Width across flats to 242

Working mediumargon,

sodium vapor,liquid sodium

Working temperature, °С 45…550

Travel speed of beam with the CPS rod, mm/s 2 to 70

Working stroke of beam with actuator, mm to 1,030

CPS rod dropping time, s not more than 1

Mass of CPS rod being transferred, kg to 70

Assigned lifetime, yrs to 30

BN-800 Control Rod Drive Mechanisms

Drive mechanisms along with reactivity control rods are designed to operate as part of the reactor control and protection system. Along with the system, they ensure reactor startup, automatic power control and switching it from one level to another.

They also provide compensation for fuel burnup in core and scheduled or emergency reactor trip.

Overpack Transfer Machine (OTM)

The overpack transfer machine is designed to carry out transfer-and-process operations with RBMK-1000 spent nuclear fuel overpacks in dry SNF storage compartments of RBMK-1000 and VVER-1000.

OTM Load-carrying capacity, kg 4,000

Rail track gage, mm 2,000

OTM travel speedon the rail track, m/s (m/min)— basic speed, not less than— creep speed, not more than

0.3 (18.0)0.003 (0.18)

Deviation from the OTM nominal position after stopping at the setpoint, mm, not more than

±5

Platform and gate drive electromechanical

Movable shielding drive hydraulic

OTM mass (without a load), kg 66,000

The container is intended to hold and store the overpacks and shim rods in the storage pool.

Container overall dimensions, mm— height— diameter

3,5001,460

Number of container housings, pcs 72

Container mass, kg 2,350

26 27

Refueling Mechanism

The reloading mechanism is designed to insert and remove the assemblies to be reloaded from the cells of the pressure header and elevator thimbles and to rotate them. Additionally, the reloading mechanism can be used as the sampler for monitoring of fuel pin leak-tightness of assemblies being reloaded.

Primary Coolant Sample and Makeup Water Preparatory Complex

The primary coolant sample and makeup water preparatory complex is a part of the automated chemical monitoring system at VVER-1000 NPPs. It is designed to prepare and deliver a sample to be analyzed to automatic electrochemical monitoring sensors.


Overall dimensions, mm— height— length— width

13,200808

1,365

Gripping device travel, mm 3,670

Mass, kg 5,300

Carriage nominal travel, mm— SCIE— FDCIE

9,56223,485

Carriage travel speed, m/min— basic speed— creep speed (at reaching limit positions)

7.0 ± 0.51.7 ± 0.5

The inclined elevator of shielded chamber (SCIE) is designed to transfer SFAs, leak-tight over-packs, leak-tight thin-walled overpacks, CRDM thimbles with grippers, CPS rods with overpacks, as well as steel and boron shielding assemblies from the receiving section of the spent fuel storage pool to the shielded chamber and back.

The inclined elevator of the fuel discharge cell (FDCIE) is designed to transfer SFAs, leak-tight overpacks, CRDM thimbles with grippers, CPS rods with overpacks, as well as steel and boron shielding assemblies from the fuel discharge cell to receiving section of spent fuel storage pool and back.

BN-800 Power Unit Inclined Elevators

28 29

Assembly Transfer Mechanism

The assembly transfer mechanism is designed to remotely reload core assemblies in the ex-reactor reloading channel of fast reactors.

Assembly total lifting height, m 7.635

Time of removal (insertion of assembly), min 4.6

Load-carrying capacity, kg 610


9.54.51.7


Mass, kg 9,160

Loading/Unloading Elevators

The loading/unloading elevators are designed to transfer both fresh and SFAs during reactor reloading from reactor core (the area served by the reloading mechanism) to elevator reloading channels (the area served by the reloading machine of the reloading box) and back.



14,681876

1,650

Working mediumargon,

sodium vapor,liquid sodium

Working temperature, °C 45…550

30 31

Fuel Handling Drums with Drives and Equipment

The fuel handling drums with drives and equipment are designed to handle fast reactor assemblies.

The fresh fuel drum is designed to contain, store and heat the assemblies prior to loading into the reactor.

The spent fuel drum is intended to contain, store and cool down the spent assemblies.

Rotary speed of drum rotors, rpm— basic speed— creep speed

0.11530.0288

Time of aligning the drum rotor slots below the reloading channels (through 7 slots), s, not more than

7

Number of drum rotor slots 234


Spent fuel drum

Overall dimensions, mm— height— diameter

5,6204,270

Drum mass, kg 69,081

Fresh fuel drum

Overall dimensions, mm— height— diameter

5,5454,140

Drum mass, kg 44,500

The reloading container is designed to carry out along with the control system reloading of highly radioactive solid waste from the shielding container to the cells of the KhTRO-3 pool, providing biological shielding of the personnel.

Load-carrying capacity of the rotary table, N

150,000

Time of aligning the CPS-rod-and-thimble container adjacent slot below the gate, min, not more than

1

Container overall dimensions, mm— height— diameter

4,7062,105

Shielding container mass, kg 62,500


Load-carrying capacity, N 3,000

Gripper working travel, mm— above the shielding container— above the storage cells (max)

5,33110,852

Container overall dimensions, mm— height— length— width

6,3701,9551,540

Reloading container mass (calculated), kg

19,700


Equipment of the KhTRO-3 Solid Radioactive Waste Storage Pool for the BN-800 Power Unit

The shielding container is designed to transfer the CPS-rod-and-thimble container with highly radioactive solid waste from the spent fuel storage pool to the KhTRO-3 pool and to provide along with the control system, removal of these assemblies from the container, ensuring bio-logical shielding of the personnel.

32

Abbreviations

CPS AR – Control and Protection System Absorber Rod

FA – Fuel Assembly

SFA – Spent Fuel Assembly

joint stock company “afrikantov okb mechanical engineering ... · 4 5 artesian pumps and...

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