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JAEA-ISCN Development Programs of Advanced NDA Technologies of Nuclear Material
October 24, 2014
Michio Seya, Naoki Kobayashi, Yosuke NaoiRyoichi Hajima, Kazuhiko Soyama,
Masatoshi Kureta, Hironobu Nakamura, Hideo Harada
Japan Atomic Energy Agency
Introduction
2
Diagram for JAEA-ISCN Development Programs of Advanced NDA Technologies of NM
MEXTMinistry of Education, Culture,
Sports, Science and Technology
ISCN
QuBS
R&D: (A)NRF NDA Technology using LCS
Gamma-rays (Intense Mono-energetic Gamma-rays)
NSEC/J-PARC/TRP
R&D: (B)Alternative to 3He Neutron Detection Technology, using
ZnS/B2O3 Ceramic Scintillator
NSEC
R&D: (C)NRD using NRTA and NRCA
JAEA
ISCN: Integrated Support Center for Nuclear Nonproliferation and Nuclear Security
QuBS: Quantum Beam Science Research Center
J-PARC:Japan Proton Accelerator Research Complex
NSEC: Nuclear Science and EngineeringResearch Center
TRP: Tokai Reprocessing Plant
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JAEA-ISCN Development Programs of Advanced NDA Technologies of Nuclear Material
R&&&&D
Order
of
Pres.
Development Programs
(A) 2NRF NDA Technology using LCS Gamma-rays (Intense Mono-energetic Gamma-rays)
(B) 3Alternative to 3He Neutron Detection Technology, using ZnS/B2O3 Ceramic Scintillator
(C) 1 NRD using NRTA and NRCA
1. NRD using NRTA and NRCA(JAEA/JRC-IRMM Collaboration)
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NRD: Neutron Resonance Densitometry
What is NRD?What can be quantified by NRD?
NRD
6
NRD: A NDA method to quantify the amount of special nuclear materials(U/Pu) (each of U/Pu isotopes)in sampleswith unknown elemental and isotopic composition, (such as melted fuel debris generated in severe
accidents of nuclear reactors)
NRD : A non-destructive mass spectrometry method
NRD: Neutron Resonance Densitometry
NRCA((((NRCA: Neutron Resonance Capture Analysis))))
Quantification of (U/Pu) Isotopes by Analyzing Transmitted Neutrons
with Information of Resonance
Absorptions by Isotopes
NRTA((((NRTA: Neutron Resonance Transmission Analysis))))
Concept of NRD
Pulsed Neutron Beams
Measurement Object(NM in thin disk-type
container)
Transmitted Neutrons
Neutron
Detector
Pulsed Neutron Beams
Measurement Object
Gamma-ray emitted from Neutron
Absorption Reaction of Isotopes
mixed with NM
Gamma-ray
Detector
Quantification of Mixed-in Isotopes by Analyzing Emitted Gamma-rays
from Neutron Absorption Reactions(Analysis of NRTA is corrected with
the amount of neutron absorbers.)
NRD
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Areal Isotope Densities(Amount of Isotopes) Fixed by NRTA
NRD
8
Measurement Object of NRTANRD
Incident neutron beam
Transmitted neutrons
A thin(~2㎝㎝㎝㎝) disk-type containerwith particle-like melted fuel debris
Particle-like melted fuel debris in a thin (~2㎝㎝㎝㎝) disk-type container
Measurement of NRTA9
Achievable Statistical Uncertainty of NRTA
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Pu238 Pu239 Pu240 Pu241 Pu242 U235 U238
Sta
tist
ical
Un
cert
ain
ty o
f Is
oto
pe
Den
sity
(%
)
0.0
0.2
0.4
0.6
0.8
1.0
Measurement period of 20 min
Neutron source intensity of 1012 n/sec
< 1% for each Pu and U isotopes
NRD
Measurement Object: Spent nuclear fuel (40GWd/t), 56Fe (9 wt%),natB (2.5 wt%)
(Diameter (Φ):30 cm, Thickness (t) = 1 cm, Weight ~4 kg)
Influence of Thickness and Particle Size on Accuracy of NRTA
NRD
Zero Approximation
Uniform Density Plate
First Approximation
Inhomogeneous Density Parts
((((Thickness Effect))))((((Particle Size Effect))))
Material density distribution seen from
incident neutrons
A thin(~2㎝㎝㎝㎝) disk-typecontainer with
particle-like MFD
Effects of these factors on precision of NRTA is about 2% in the case of thickness is less than 2㎝㎝㎝㎝.
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NRD
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Uncertainty of Total Pu with10B Concentration and Thickness
Uncertainty of NRD for total Pu with 10% 10B concentration and 2cm thickness Is about 1% .
The quantity of the containing isotopes is determined from a obtained gamma-ray spectrum.
NRCA (PGA) for Quantification of Impurities
Pulsed Neutron Beams
Measurement Object
Gamma-ray emitted from
Neutron Absorption Reaction
of Isotopes mixed with NM Gamma-ray Detector
NRD
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Nucleus ReactionEnergy of
Prompt γ ray1st Neutron Resonance
Capture,
(n,a)1H 1H(n, g)2H 2223 keV ― 0.332 b
10B 10B(n, ag)7Li 478 keV 170 keV (3839 b)
27Al 27Al (n, g) 28Al 7724 keV 6 keV 0.229 b
28Si 28Si (n, g) 29Si 4934 keV 32 keV 0.169 b
56Fe 56Fe (n, g)57Fe 7646 keV 1 keV 2.59 b
53Cr 53Cr (n, g)54Cr 8885 keV 4 keV 18.4 b
58Ni 58Ni (n, g)59Ni 8999 keV 7 keV 4.62 b
1st Neutron Resonance energy >> 50 eV for contaminated isotopes
Prompt g ray energy >> 661 keV of 137Cs except 478 keV by 10B
Containing Isotopes and Prompt Gamma-ray Energies
NRD
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●●●● High energy resolution●●●● High counting rate●●●● High peak-to-Compton ratio
Detector length
0 mm25 mm50 mm80 mm
100 mm127 mm
High S/N ratio !
Sample(Cs-137)
Main LaBr3(Ce) Detector
Back-catcher Detector
Pulsed Neutron Beam
Backscattering Gamma ray
Detector length
LaBr3 spectrometer with Back-catcher
B-10 (478 keV)
Energy spectra of the detector with a Cs-137 source
Concept of Gamma-ray Spectrometer to quantify 10B
NRD
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Estimated Accuracy of NRD(as a result of collaboration studies)
NRD
About 3% for the amount of U/Pu in particle like Melted Fuel debris
Validation of NRD at GELINA
GELINA at JRC-IRMM
NRD
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0.000
0.005
0.010
Texp
Ttheory
238U 238U238U
235U
Tra
nsm
isso
n
235U
0 5 10 15 20 25 30 35 40-4
0
4
Res
idua
l
Neutron energy / eV
Measurement of the CBNM standard 446
Areal density
NRTA Reference (IDMS)
235U (5.063 ± 0.090) x 10
-4 at/b (5.0326 ± 0.0080) x 10
-4 at/b
238U (1.062 ± 0.010) x 10
-2 at/b (1.0628 ± 0.0015) x 10
-2 at/b
Demonstration of NRD at GELINA
new experimental target hut at 13 m
GELINA at JRC-IRMM
(Demonstration experiments; in the beginning of March 2015 at GELINA)
With Mini Workshop on NRD and active neutron NDA
target (sample)
LaBr3 scintillation detector (JAEA)
NRD
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� Neutron Time-of-Flight (TOF) FacilityInstitute for Reference Materials and Measurements @ Belgium
electron LINAC (aver. 100 MeV)
neutron source
U (target) + water (moderator)
# of neutrons @source
3 x 1013 n/s
neutron TOF technique
- neutron TOF � neutron energy
GELINA ((((JRC-IRMM))))
ELECTRON LINAC
TARGET HALL
FLIGHT PATHS (SOUTH)
FLIGHT PATHS (NORTH)
NRD
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Mini-Workshop (Tentative) Title: Demonstrations of NRD / Active Neutron NDA Technologies
for Nuclear Material using Pulsed Neutron Beam
Date : 4 and 5 -March-2015Place: JRC-IRMM (Geel, Belgium)
Agenda (Draft)
Day 1 (PM1:00-PM5:00) Day 2 (AM9:00-PM3:00)
(AM) (AM)4. Demonstration of NRD(Part II)
Stop measurements / Showing the analysis5. Session (2)
NRD and active neutron NDA technologies
(Lunch)
(PM)1. Opening Remarks of the Workshop (JRC / JAEA)2. Introduction of NRD (JRC / JAEA)3. Demonstration of NRD(Part I)
Selection of samples to be measured by NRDStarting of measurement
4. Session (1) NRTA and NRCA(PGA)
(PM)6. Discussion on future prospective of active
neutron NDA7. Closing Remarks
Demonstration / Mini-Workshop(Tentative)
NRD
JAEA/JRC-IRMM welcome your participation. 20
Neutron detector for counting transmitted neutrons
NRTA Measurement container with
particle-like Debris
Gamma-ray detector
Beam dump
Pulsed neutron beams
n ~1012 n/sec
Sample for NRCA
A 30 MeV electron accelerator for pulsed
neutron generation
Target / Moderator
A thin disk-type container for classified particle-like debris for the NRD system
Total Area : 200 m2
1F Machine Room: 15 m × 12 m = 180 m2
2F Control Room: 5 m × 4 m = 20 m2
A Picture of a Practical NRD SystemNRD
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Grinding (Crashing)
Machine
(to be developed)
(Small rock-like debris
into particle-like debris)
a container for classified particle-
like debris
Collection of Particle-like Melted Fuel Debris
Classification of particle-like debris by sizes with sieves
Rock of solidified melted
fuel and fine debris
Particle-like debris will be separated
by particle size in a water.
Small rock-like
debris
Particle-like debris
Debris will be taken
away by breaking,
drilling, cutting etc.
(Just a Possible Idea)
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NRD
Preparation of Precise Measurement of Nuclear Material in Particle-like Debris
A large container for classified
particle-like debris
Thin disk-type containers for classified particle-like
debris for NRTA
Removing of
particle-like debris
Classification of particle-like debris by sizes with sieves
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Making a large batch of
particle-like debris by
mixing
Samples for NRCA to quantify 10B etc.
・
・・
NRD
2. NRF NDA Technology using LCS Gamma-rays (Intense Mono-energetic Gamma-rays)
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ElectronLaser photon
Scattered photon
(X-ray /Gamma-ray)
• Energy depends on energies
of electrons and laser photons.
• Pencil-like beam
• Energy tunable
• Monochromatic X-ray /gamma-ray beam
(dE/E < 1%)
gamma-ray energy (keV)
peak b
rillia
nce (
ph/m
m2/m
rad
2/s/
0.1
%BW
)
0
1e+19
2e+19
3e+19
4e+19
5e+19
1500 1600 1700 1800 1900 2000 2100 2200 2300 2400
εn=0.1mm-mrad
E
dE
Calculated Energy Spectrum
ERL based LCS X-/gamma-ray source has high flux and sharp energy width.
LCS X-ray / Gamma-ray Beamusing ERL ((((Energy Recovery Linac))))
NRF-NDA
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Electron Gun
Energy Recovery Linac(Super-Conducting Cavity)
(9-cell x 2 cavity)
ExperimentRooms
Laser Enhancement
Cavity
Goals of Basic Technology Demonstration Stage(Electron Beam = 26 MeV, 10 mA)
�LCS Gamma-ray (~ 10keV) Flux ~ 1x1011 ph/s�PE/E < 1%
LCS Gamma -rays
Injector
Demonstration of High Intensity Gamma-rays by an LCS Demo. System
Demonstration in March 2014 at Tsukuba (Japan)
35 MeV electron
s High PowerLaser Oscillator
NRF-NDA
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Next Generation ERL((((350 MeV))))
gamma-rays
Laser Enhancement Cavityfor LCS gamma-ray generation
350 MeV electrons
3 loops
A Future LCS Gamma-ray Source with 3-loop ERL
Electron Beam=350 MeV, 10 mALCS Gamma-ray ((((2-3 MeV))))�Flux ~ 1x1013 ph/s�PE/E < 1%
~ 25 m
High PowerLaser Oscillator
(for Intense Mono-energetic 2-3 MeV Gamma-rays)
NRF-NDA
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LCS Gamma-rays with
Energy 2 - 3 MeV
Next Generation ERL
(350 MeV)
Laser Enhancement Cavity
Cargo
ContainerGamma-ray
Detectors
High Power Laser Oscillator
For detection of NM hidden behind heavy shield in cargo containers
Examples of Possible Applications of NRF NDA System using LCS Gamma-rays ((((1))))
(Nuclear Security)
Nuclear Material
in Heavy Shield
NRF-NDA
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Examples of Possible Applications of NRF NDA System using LCS Gamma-rays ((((2))))
(Safeguards: Material Accountancy)
NRF-NDA
Laser Enhancement
Cavity
For precise measurement of NM isotopes in SFA / MFD in a canister
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Transmission NRF Assay of An Isotope ((((239Pu etc.))))
(For an Example: Assaying 239Pu in Melted Fuel using Witness Plate)
Energy
NRF signal decreases due to
depletion of the gamma-ray
beam.
The amount of decrease of
NRF signal is proportional to
the amount of 239Pu in the
gamma-ray path.
NRF-NDA
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3. Alternative to 3He Neutron DetectionTechnology, using ZnS/B2O3 Ceramic
Scintillator
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ZnS/10B2O3 Ceramic Scintillator Neutron Detector
ZnS/10B2O3 Ceramic Scintillator
Sheet
Signal Processor
32
Demonstration Test:
in march 2015
10B2O3/ZnSCeramic Scintillator(Rectangular Area)
An axial sectional view of the designed ASASOverall View
We have been fabricating the alternative HLNCC type NDA system,
ASAS (Alternative Sample Assay System) and preparing a demonstration
test to measure MOX powder or Pu nitrate solution in a sample vial.
Shift Register for IAEA Demonstration (JSR-15)
TTL
ASAS ((((Alternative INVS))))
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Demonstration ((((Comparison)))) Test of ASAS with INVS
Demonstration (Comparison) Test: in march 2015
Current INVS ASAS(Alternative INVS)
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Using MOX in TRP
Thank you for your attention.
These R&D programs are sponsored by MEXT (Ministry of Education, Culture, Sports, Science
and Technology) of Japan.
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