LES MESURES NUCLÉAIRES NON DESTRUCTIVES POUR LE CONTRÔLE DES DÉCHETS RADIOACTIFS, L ASSAINISSEMENT ET LE DÉMANTÈLEMENT DES INSTALLATIONS
|
|
- Leslie Evans
- 5 years ago
- Views:
Transcription
1 LES MESURES NUCLÉAIRES NON DESTRUCTIVES POUR LE CONTRÔLE DES DÉCHETS RADIOACTIFS, L ASSAINISSEMENT ET LE DÉMANTÈLEMENT DES INSTALLATIONS Bertrand PEROT, CEA DEN CADARACHE EFFMIN 4 MARSEILLE, FRANCE JUILLET 2016 EFFMIN4 MARSEILLE JUILLET PAGE
2 CONTENTS Photon imaging Gamma-ray spectroscopy Passive and active neutron measurements Coupling measurement results R&D on new techniques EFFMIN4 MARSEILLE JUILLET 2016 PAGE 2
3 TRANSMISSION RADIOGRAPHY AND DENSITOMETRY LINAC 60 Co source E ~ 1.25MeV Detection system PAGE 3 ln 0 ( E ) / L 0 Photon source EFFMIN4 MARSEILLE JUILLET 2016 PAGE 3
4 PHOTON TRANSMISSION TOMOGRAPHY Projections >1000 on 360 Reconstructed 2D cross sections EFFMIN4 MARSEILLE JUILLET 2016 PAGE 4
5 60 CO IMAGING: PRECISE DENSITY BUT LONG TRANSEC: historic 60 Co tomography system of LMN, CEA DEN CADARACHE 50 mm 120 mm 190 mm 260 mm 330 mm 400 mm 470 mm 540 mm Density mm 680 mm 750 mm 820 mm EFFMIN4 MARSEILLE JUILLET 2016 PAGE 5
6 HIGH ENERGY X-RAY IMAGING WITH A LINAC Bremsstrahlung X-ray beam LINAC Lead collimator Object (waste drum ) Scintillation plate Mirror CCD camera CINPHONIE: recent high energy imaging system of LMN, CEA DEN CAD CINPHONIE Vs. TRANSEC: Radiography: 240 faster (40 h 10 min) Tomography: 36 faster (15 h 25 min) 9 MeV LINAC (15 Gy/min at 1m) Moving platform (up to 2 tons) Scintillation plate (800 x 600 mm²) Gadox Gd 2 O 2 S ; 1.5 mm Nicolas Estre, Daniel Eck, Jean-Luc Pettier, Emmanuel Payan, Christophe Roure and Eric Simon, High-Energy X-Ray Imaging Applied to Non Destructive Characterization of Large Nuclear Waste Drums, ANIMMA 2013, June 2013, Marseille, France PAGE 6
7 HIGH ENERGY IMAGING OF LARGE CONCRETE DRUMS Concrete waste: density > 2 Less than 1 s per single radiography Radiography Tomography 1,2 tonne H=1,2m =0,84m EFFMIN4 MARSEILLE JUILLET 2016 PAGE 7
8 IN SITU HIGH ENERGY X-RAY IMAGING Bituminized waste drum characterization at BELGOPROCESS facility, Belgium Radioscopy of the corium - water interaction Nuclear accident studies, KROTOS facility, CEA Cadarache Water surface EFFMIN4 MARSEILLE JUILLET 2016 PAGE 8
9 COMPUTED GAMMA EMISSION TOMOGRAPHY?????????????????????????????????????? Transmission tomography 2D density map Gamma spectra Sinogram R. Thierry, J.L Pettier and L. Desbat, Simultaneous compensation for attenuation, scatter and detector response for 2D-emission tomography on nuclear waste with reduced data, 1 st World Congress on Industrial Process Tomography, Buxton, Greater Manchester, April 14-17, E1 : , 1999 Emission tomography 2D activity map PAGE 9
10 PHOTON IMAGING GAMMA SPECTROSCOPY PASSIVE AND ACTIVE NEUTRON MEASUREMENTS COMBINED MEASUREMENTS R&D EFFMIN4 MARSEILLE CEA JUILLET PAGE 10
11 GAMMA-RAY SPECTROSCOPY Radioactive object (e.g. a waste package) Detector and electronics A Gamma spectrum A ( E ) Activity Sn ( E ) ( E ) I( E ) T Net area S n Sn(E) Compton background EFFMIN4 MARSEILLE JUILLET 2016 PAGE 11
12 RADIOACTIVE WASTE CHARACTERIZATION Specific gamma spectroscopy stations the laboratory Part of combined measurements e.g. for ANDRA Super-Controls with X-ray imaging and neutron assay EFFMIN4 MARSEILLE JUILLET 2016 PAGE 12
13 IN SITU SPECTROSCOPY IN NUCLEAR REACTORS Historic activity > 300 campaigns (end of 70 s) EDF and foreign power plants EMECC device & software Intermediate activities (1 MBq/m² 100 GBq/m²) Pipes, steam generators, heat exchangers Characterization of a whole plant (all circuits) EMECC Deposited or volumetric activities (GBq / m² or m 3 ) Experimental qualification by EDF Support to OSCAR contamination transfer code Steam generator spectra (Ge vs. CZT) EFFMIN4 MARSEILLE JUILLET 2016 PAGE 13
14 IN SITU SPECTROSCOPY OF LARGE COMPONENTS Uranium hold-up measurement in a heat exchanger Segmented gamma spectrometry Vessel contamination and activation Underwater HP Ge gamma-ray spectroscopy SFR cold trap characterization HP Ge + CZT in inspection hall Characterization of activated components TORE SUPRA wastes HP Ge EFFMIN4 MARSEILLE JUILLET 2016 PAGE 14
15 IN SITU SPECTROSCOPY OF NUCLEAR MATERIALS Dismantling operations Fuel fabrication and reprocessing units Fissile mass estimation in a reprocessing unit HP Ge detector isotopic composition, activity or mass CZT probe introduced in glove boxes localization Characterization of Pu in glove boxes of a Pu fuel fabrication facility HP Ge detector CZT probe EFFMIN4 MARSEILLE JUILLET 2016 PAGE 15
16 IN SITU SPECTROSCOPY FOR BUILDINGS Inside After removing all components Outside Walls control High efficiency HP Ge with tungsten shield EFFMIN4 MARSEILLE JUILLET 2016 PAGE 16
17 PHOTON IMAGING GAMMA SPECTROSCOPY PASSIVE AND ACTIVE NEUTRON MEASUREMENTS COMBINED MEASUREMENTS R&D EFFMIN4 MARSEILLE CEA JUILLET PAGE 17
18 MIXED PASSIVE & ACTIVE NEUTRON CELL (R&D) PROMETHEE VI R&D cell LMN, CEA DEN Cadarache Christian Passard et al., PROMETHEE: An Alpha Low Level Waste Assay System Using Passive And Active Neutron Measurement Methods, NUCLEAR TECHNOLOGY VOL. 140 DEC A. Mariani et al., The help of simulation codes in designing waste assay systems using neutron measurement methods: Application to the alpha low level waste assay system PROMETHEE 6, Nuclear Instruments and Methods in Physics Research B 211 (2003) Fanny Jallu et al., Alpha-Particle Low-Level Waste Control: Improvement of the PROMETHEE 6 Assay System Performances, Nuclear Technology Vol. 153 Jan EFFMIN4 MARSEILLE JUILLET 2016 PAGE 18
19 PASSIVE NEUTRON MEASUREMENT Total counting Spontaneous fission + (,n) neutrons 242 and 244 Cm, 238, 240 and 242 Pu, 241 Am (+ 238 U if mass > kg) Coincidence counting Spontaneous fission neutrons only 242 and 244 Cm, 238, 240 and 242 Pu (+ 238 U) Counts Real coincidences R A Accidental coincidences A A Time R+A Gate a few 10 µs Delay 1 ms A Gate (same duration as R+A gate) EFFMIN4 MARSEILLE JUILLET 2016 PAGE 19
20 ACTIVE DIFFERENTIAL DIE AWAY TECHNIQUE Prompt zone de mesure des neutrons prompts de neutrons fission zone mixte Background Bruit de fond uranium 235 m = 30 mg uranium 235 m = 60 mg uranium 235 m = 122 mg uranium 235 m = 242 mg Signal (c/s) 1000 Delayed zone de mesure des neutrons retardés de fission neutrons zone de saturation des chaînes d'acquisition inexploitable Temps Time après after l'impulsion neutron pulse de neutrons (s) (µs) Prompt and delayed neutron signals 235 U and 239 Pu discrimination Prompts neutrons 235 U, 239 and 241 Pu Delayed neutrons 235 U, 239 and 241 Pu U and 232 Th EFFMIN4 MARSEILLE JUILLET 2016 PAGE 20
21 CALIBRATION WITH DIFFERENT MATRIX MATERIALS Passive detection Active neutron signal F. Jallu et al. / Nuclear Instruments and Methods in Physics Research B 271 (2012) A.-C. Raoux et al. / Nuclear Instruments and Methods in Physics Research B 266 (2008) R. Antoni et al. Matrix effect correction with internal flux monitor in radiation waste characterization with the Differential Die-away Technique, IEEE Transactions on Nuclear Science, Vol. 61, No. 4 (2014) EFFMIN4 MARSEILLE JUILLET 2016 PAGE 21
22 PASSIVE & ACTIVE NEUTRON CELL Pulsed DT neutron generator GENIE 36 SODERN, n/s Polyethylene Graphite Neutron generator Lead ring around the generator Turntable 99 3 He counters in 3 detection blocks (CH 2 + Cd) empty cell ~ 23% Lead shield Graphite SYMETRIC measurement cell LMN, CEA DEN Cadarache ANDRA -CEA Super-controls EFFMIN4 MARSEILLE JUILLET 2016 PAGE 22
23 IN SITU PASSIVE / ACTIVE NEUTRON SYSTEMS PACCMAN, COQUINA: active neutron interrogation systems plugged to hot cells to assess Pu and U in high level wastes 3 He+CH 2 +Cd detection blocks Graphite measurement cavity Neutron generator (hole) Detection blocks (U shape) Neutron generator in a graphite reflector PACCMAN COQUINA LMN, CEA DEN CADARACHE ATALANTE, CEA DEN MARCOULE EFFMIN4 MARSEILLE JUILLET 2016 PAGE 23
24 IN SITU NEUTRON MEASUREMENTS Characterization of large components in uranium enrichment facilities (UF 6 gas diffusion technology) Passive neutron measurement of the uranium hold-up in UF 6 compressors Passive (and active) neutron measurements of uranium holdup in an UF 6 crystallizer Measurement of the uranium enrichment in an UF 6 container by active neutron interrogation F. Jallu et al., Dismantling and decommissioning: The interest of passive neutron measurement to control and characterise radioactive wastes containing uranium, Nuclear Instruments and Methods in Physics Research B 271 (2012) EFFMIN4 MARSEILLE JUILLET 2016 PAGE 24
25 PHOTON IMAGING GAMMA SPECTROSCOPY PASSIVE AND ACTIVE NEUTRON MEASUREMENTS COMBINED MEASUREMENTS R&D EFFMIN4 MARSEILLE CEA JUILLET PAGE 25
26 RADIOACTIVE WASTE CARACTERISATION X-RAY RADIOGRAPHY + SPECTROSCOPY + PASSIVE NEUTRON COUNTING X-ray radiography PEGAZE 100 L historic waste drums, CEA DEN CADARACHE -ray Spectro. Passive Neutron Coinc. Counting F. Jallu et al. / Nuclear Instruments and Methods in Physics Research B 271 (2012) EFFMIN4 MARSEILLE JUILLET 2016 PAGE 26
27 COMBINED MEASUREMENT SYSTEM RADIOGRAPHY + SPECTROSCOPY + ACTIVE & PASSIVE NEUTRON CELL > 60,000 historic 225 L bituminized waste drums (Marcoule, France) Non Destructive Assay performance study Low resolution gamma radiography ( 60 Co) BGO detector + Fe collimator 60 Co source + lead plates Filling height Matrix density Gamma spectroscopy, radionuclides 241 Am activity Coaxial HP Ge (100% rel. eff.) Planar HP Ge + BGO Compton suppression Passive & active neutron cell Pu, U Graphite and polyethylene cell 99 3 He counters + Pb and Cd shields Pulsed n/s neutron generator Open geometry + lead shield Waste drum Iron collimators B. Pérot, J.-L. Artaud, C. Passard, A.-C. Raoux, Experimental Qualification With a Scale One Mock-Up of the Measurement and Sorting Unit for Bituminized Waste Drums, PAGE 27
28 COUPLING MEASUREMENT RESULTS Neutron measurements passive active Gamma imaging Density, filling height Gamma-ray spectroscopy U, Th 240 Pu 239 Pu Waste production data Matrix composition, homogeneity Isotopic composition of U and Pu Ratios between beta-gamma RNs and non detectable radionuclides Total alpha activity 241 Am Individual beta activities 137 Cs, 60 Co, 154 Eu... PAGE 28
29 PHOTON IMAGING GAMMA SPECTROSCOPY PASSIVE AND ACTIVE NEUTRON MEASUREMENTS COMBINED MEASUREMENTS A FEW R&D TOPICS EFFMIN4 MARSEILLE CEA JUILLET PAGE 29
30 DUAL ENERGY IMAGING (SATURNE LINAC PROJECT) Mass attenuation coefficient µ/ LINAC acquisitions at 15 MeV and 9 MeV µ 15MeV (E~ 6 MeV) / µ 6MeV (E~4 MeV) Atomic number Z (simulation of a 870 L drum) 3 Density (simulation of a 870 L drum) EFFMIN4 MARSEILLE JUILLET 2016 PAGE 30
31 HIGH ENERGY X-RAY TOMODENSITOMETRY Attenuation up to 5 decades (40 cm steel) Radiography and 2D plane tomography 3D helicoidally tomography 0.5 to 2 mm spatial resolution 1 h (2D) to several days (3D) acquisitions Collimated CdTe detectors Simulations of a 5 m 3 concrete waste package 9 MeV LINAC 15 MeV LINAC EFFMIN4 MARSEILLE JUILLET 2016 PAGE 31
32 ACTIVE PHOTON INTERROGATION: PHOTOFISSION U and Pu measurement in large concrete waste packages High energy X rays produced by an electron LINAC (photofission threshold ~ 6 MeV) Delayed neutron counting between the pulses Delayed gamma-ray spectroscopy after stopping irradiation Setup with 5 HP Ge detectors 100 g U in the center of the 870L drum 2h irradiation + 3h counting Useful delayed gamma signal (MCNP simulation) Waste package passive gamma background 15 MV Linac beam (870 L drum) U in the center Background & detection limit - 1 detector Backgr. & detection limit - 5 detector cluster ray (kev) B (counts) L D (counts) L D (g 235 U) B (counts) L D (counts) L D (g 235 U) , , , , , , , , , , , , , , , , , , , , , , , ,00 E. Simon, F. Jallu, B. Pérot, S. Plumeri, Feasibility study of fissile mass quantification by photofission delayed gamma rays in radioactive waste packages using MCNPX, submitted to Nuclear Instruments and Methods in Physics Research A PAGE 32
33 NEUTRON ACTIVATION ANALYSIS Toxic chemical or matrix material characterization in radioactive wastes PGNAA Prompt Gamma Neutron Activation Analysis Pulsed neutron generator + HP Ge gamma-ray detector Neutron flux A few 10 µs Up to few ms Time Fast neutrons during the pulses (n,n ) Thermal neutrons between pulses (n,) (+ deactivation gamma rays after irradiation) Mercury sample Mercury nitrate sample No sample Difference Hg capture gamma rays Hg sample Neutron generator 30% HPGe with 6 Li shield J.-L. Ma et al., Prompt Gamma Neutron Activation Analysis of toxic elements in radioactive waste packages, Applied Radiation and Isotopes 70 (2012) 1261 REGAIN cell, CEA DEN CAD, LMN EFFMIN4 MARSEILLE JUILLET 2016 PAGE 33
34 CEA- FZJ COLLABORATION ON PGNAA MEDINA PGNAA cell FZJ, Germany, GENIE 16 neutron generator and ~ 100% HP Ge EXP / MCNP comparisons MCNP performance optimization Fission delayed (see next slide) POSTER Tangi NICOL EFFMIN 4 tangi.nicol@cea.fr T.Nicol, C. Carasco, B. Perot, J.L. Ma, E. Payan et al., Quantitative comparison between PGNAA measurements and MCNPX simulations, Journal of Radioanalytical and Nuclear Chemistry, DOI /s PAGE 34
35 NEUTRON-INDUCED FISSION DELAYED -RAY YIELDS Gamma spectra of 235 U and 239 Pu samples measured in REGAIN between neutron pulses 95 Y 235 U 239 Pu 90 Rb- 90m Rb 132 Sb- 132m Sb 89 Rb REGAIN and its MCNP model 94 Sr 136 I- 136m I Gamma spectra after irradiation Low background -spectroscopy lead shelter 89 Rb 89 Rb 92 Sr T. Nicol, B. Pérot, C. Carasco, E. Brackx, A. Mariani, C. Passard, E. Mauerhofer, A. Havenith, 235 U and 239 Pu characterization in radioactive waste using neutron-induced fission delayed gamma rays, Nuclear Instruments and Methods in Physics Research A 832 (2016) PAGE 35
36 FISSION DELAYED -RAY DETECTION LIMITS MCNP calculations (MEDINA, 225 L drums) Active background (MEDINA, 225 L concrete mockup drum, measurement between pulses) Fission rate per volume unit (10 g 239 Pu) Detection limits in a 225 L concrete drum, with a n/s emission, 7200 s irradiation, 900 s post irradiation counting E (kev) Precursor T 1/2 (s) DL 239 Pu (g) DL 235 U (g) Rb- 90m Rb Y Sb- 132m Sb Rb I- 136m I Sr Sr Tc- 134 I T. Nicol, B. Pérot, C. Carasco, E. Brackx, A. Mariani, C. Passard, E. Mauerhofer, A. Havenith, 235 U and 239 Pu characterization in radioactive waste using neutron-induced fission delayed gamma rays, Nuclear Instruments and Methods in Physics Research A 832 (2016) PAGE 36
37 THE ASSOCIATED PARTICLE TECHNIQUE (APT) Alpha detector (position sensitive) Neutron TOF (alpha-gamma coincidence) T(D,n) 14 MeV neutron generator Inspected object Tagged neutrons Volume of interest Volume of interest Built-in segmented alpha detector d n Tritium target t Gamma-ray detector Gamma spectrum (selected volume) Unfolding (with a calibration database) B. Pérot, G. Sannié, Détection neutronique de matières illicites avec la technique de la particule associée, Editions Techniques de l Ingénieur, RE 177, février 2015 EFFMIN4 MARSEILLE JUILLET 2016 PAGE 37
38 ORGANIC MATERIALS IDENTIFICATION (SECURITY) Atomic fractions TNT simulant measurement Explosives Illicit drugs Benign materials A. Buffler, PAGE 38
39 RADIOACTIVE WASTE MATERIAL CHARACTERIZATION Feasibility study on non-radioactive materials (experiments) Enveloppe en béton Blocs Al Gamma spectra for different TOF windows Time-of-flight (TOF) spectrum Aluminum Concrete Random backround C. Carasco, B. Pérot, A. Mariani, W. El Kanawati, V. Valkovic, D. Sudac, J. Obhodas, Material characterization in cemented radioactive waste with the associated particle technique, Nuclear Instruments and Methods in Physics Research A 619 (2010) PAGE 39
40 PERFORMANCES FOR RADIOACTIVE WASTE PACKAGES MCNP simulations for 225 L bituminized waste drums (~ 1 TBq 137 Cs) Counts (source neutron) -1 Neutron generator background ( n/s) Counts Random background Counts (source photon) -1 Radioactive waste background 100 kev threshold Counts Random background Useful signal (not visible) Energy (MeV) Time Of Flight (ns) Energy (MeV) Time Of Flight (ns)
41 PERFORMANCES FOR RADIOACTIVE WASTE PACKAGES MCNP simulations for 225 L bituminized waste drums (~ 1 TBq 137 Cs) Counts (source neutron) -1 Neutron generator background ( n/s) Counts Counts (source photon) -1 Radioactive waste background 790 kev threshold Counts Random background Useful signal (visible) Energy (MeV) Time Of Flight (ns) Energy (MeV) Time Of Flight (ns)
42 SIMULATION OF OBJECTS IN THE 225 L BITUMINIZED DRUM Object of interest W. El Kanawati, B. Perot, C. Carasco, Monte Carlo Simulation of High-Level Radioactive Waste Characterization with the Associated Particle Technique, Nuclear Instruments and Methods in Physics Research A 705 (2013) EFFMIN4 MARSEILLE JUILLET 2016 PAGE 42
43 OBJECT IN THE CENTER OF THE BITUMINIZED DRUM (MCNP) 1 detector, 60 min 10 times more counts (10 detectors or 600 min) Object of interest W. El Kanawati, B. Perot, C. Carasco, Monte Carlo Simulation of High-Level Radioactive Waste Characterization with the Associated Particle Technique, Nuclear Instruments and Methods in Physics Research A 705 (2013) EFFMIN4 MARSEILLE JUILLET 2016 PAGE 43
44 SCINTILLATORS TO REPLACE 3 HE DETECTORS Passive neutron coincidence counting for radioactive waste drums - MCNP PoliMi simulation L waste drums - 10 cm thick plastic detectors (with lead shields) - ~ 0.5 g of 240 Pu eq s acquisition time 0.2 g/cm 3 organic matrix 0.5 g/cm 3 metallic matrix Triples (multiplicity 2 coincidences) B. Simony, C. Deyglun, B. Pérot, C. Carasco, N. Saurel, S. Colas, J. Collot, Cross-talk characterization in passive neutron coincidence counting of radioactive waste drums with plastic scintillators, IEEE Transactions on Nuclear Science, Vol. 63, No. 3, June 2016 PAGE 44
45 SIMULATED PERFORMANCES (TRIPLES) Few accidental coincidences up to 10 g of Pu Neutron vs. gamma events in the triples Plutonium localization effect Good signal to noise ratio (Pu/Total) POSTER Benoît SIMONY EFFMIN 4 benoit.simony@cea.fr EFFMIN4 MARSEILLE JUILLET 2016 PAGE 45
46 CONCLUSION Radioactive and nuclear material characterization Gamma-ray spectroscopy Passive neutron counting Neutron and photon interrogation Physical and elemental characterization Imaging techniques: gamma, X-ray Neutron activation analysis NDA for D&D and radioactive waste characterization Complementary to sampling & analytic methods Sensitivity, precision, accuracy Vs. complexity, acquisition time, cost The dream team = historic operators + NDA experts + D&D operators 26 JUILLET 2016 EFFMIN4 MARSEILLE JUILLET 2016 PAGE 46
47 EFFMIN4 MARSEILLE JUILLET 2016 THANK YOU! CEA International Expert PAGE 47 Commissariat à l énergie atomique et aux énergies alternatives Centre de Cadarache F Saint-Paul-lez-Durance FRANCE T. +33 (0) Laboratoire de Mesures Nucléaires Etablissement public à caractère industriel et commercial RCS Paris B Direction de l Energie Nucléaire Département de Technologie Nucléaire Service Mesures et Modélisation des Transferts et des Accidents Graves
Study of X-ray diagnostics for corium-sodium interaction during severe accident scenario
Study of X-ray diagnostics for corium-sodium interaction during severe accident scenario PHENIICS Fest Orsay, 31 st May, 2017 Shifali SINGH DEN/DTN/SMTA/LPMA CEA, Cadarache Christophe Journeau Thesis Director
More informationNON DESTRUCTIVE CONTROLS OF RADIOACTIVE WASTE AT CEA
NON DESTRUCTIVE CONTROLS OF RADIOACTIVE WASTE AT CEA 8 th International Summer School on Nuclear Decomissionning and Waste Management 12-16 SEPTEMBER 2016, ISPRA 8th International Summer School, 12-16
More informationA Photofission Delayed γ-ray Spectra Calculation Tool for the Conception of a Nuclear Material Characterization Facility
A Photofission Delayed γ-ray Spectra Calculation Tool for the Conception of a Nuclear Material Characterization Facility D. BERNARD *, O. SEROT *, E. SIMON *, L. BOUCHER * and S. PLUMERI + Abstract The
More informationDigital simulation of neutron and gamma measurement devices
3Security of radioactive materials and transport 3 2 Digital simulation of neutron and gamma measurement devices A.-L. WEBER (IRSN) 1 - Maximum activity that a radioactive element can present without being
More informationNEW DEVELOPMENTS OF AUTORADIOGRAPHY TECHNIQUE TO IMPROVE ALPHA AND BETA MEASUREMENTS FOR DECOMMISSIONING FACILITIES
NEW DEVELOPMENTS OF AUTORADIOGRAPHY TECHNIQUE TO IMPROVE ALPHA AND BETA MEASUREMENTS FOR DECOMMISSIONING FACILITIES PASCAL FICHET, C MOUGEL, Y DESNOYERS, P SARDINI, H WORD DEN SERVICE D ETUDES ANALYTIQUES
More informationResearch in NDA Techniques for Waste Characterization at the JRC
1 Research in NDA Techniques for Waste Characterization at the JRC Bent Pedersen Nuclear Security Unit Institute for Transuranium Elements Joint Research Centre presented at Annual meeting of LABONET Network
More informationNeutron and Gamma Ray Imaging for Nuclear Materials Identification
Neutron and Gamma Ray Imaging for Nuclear Materials Identification James A. Mullens John Mihalczo Philip Bingham Oak Ridge National Laboratory Oak Ridge, Tennessee 37831-6010 865-574-5564 Abstract This
More informationContrabands detection with a low energy electron linac driven photoneutron source
Contrabands detection with a low energy electron linac driven photoneutron source Yigang Yang Tsinghua University, Beijing, China yangyigang@mail.tsinghua.edu.cn Outline 1. Research motivation 2. e-linac
More informationAcquisition of neutron-induced gamma signatures of chemical agents
1 SM/EN-07 Acquisition of neutron-induced gamma signatures of chemical agents B. Perot 1, C. Carasco 1, R. Vogler 2, E. Cusset 2, J.-L. Ma 1, P. Pras 2, M. Gmar 3, G. Sannie 3, S. Normand 3 1 CEA, DEN,
More informationVerification measurements of alpha active waste
Verification measurements of alpha active waste Bent Pedersen Nuclear Security Unit Directorate Nuclear Safety and Security JRC 9th Edition of the International Summer School on Nuclear Decommissioning
More informationCZT Gamma Spectrometry Applied to the In-situ Characterisation of Radioactive Contaminations
CZT Gamma Spectrometry Applied to the In-situ Characterisation of Radioactive Contaminations Alain Rocher (EDF/DPN; e-mail : alain.rocher@edf.fr) Leon Piotrowski (EDF/R&D; e-mail : leon.piotrowski@edf.fr)
More informationFISSILE MATERIALS DETECTION VIA NEUTRON DIFFERENTIAL DIE-AWAY TECHNIQUE
Applications of Nuclear Techniques (CRETE13) International Journal of Modern Physics: Conference Series Vol. 27 (2014) 1460130 (8 pages) The Authors DOI: 10.1142/S2010194514601306 FISSILE MATERIALS DETECTION
More informationQuality control of neutron-absorber materials for the nuclear fuel cycle, Principle of the JEN-3 neutron Backscattering gauge
Quality control of neutron-absorber materials for the nuclear fuel cycle, Principle of the JEN-3 neutron Backscattering gauge Hamid MAKIL (CEADRT/LIST/LCAE) Patrick BRISSET (IAEA) ICARST 2017, 24 28 April
More informationVerification measurements of alpha active waste
Verification measurements of alpha active waste Bent Pedersen Nuclear Security Unit Institute for Transuranium Elements (ITU), JRC Operational Issues in Radioactive Waste Management and Nuclear Decommissioning
More informationNon-Destructive Assay Applications Using Temperature-Stabilized Large Volume CeBr Detectors 14277
Non-Destructive Assay Applications Using Temperature-Stabilized Large Volume CeBr Detectors 14277 D. Nakazawa and F. Bronson Canberra Industries Inc., 800 Research Parkway, Meriden, CT, 06450, USA. ABSTRACT
More informationGamma signatures of the C-BORD Tagged Neutron Inspection System
Gamma signatures of the C-BORD Tagged Neutron Inspection System A. Sardet, B. Pérot, C. Carasco, G. Sannié, S. Moretto, G. Nebbia, C. Fontana, F. Pino, A. Iovene, C. Tintori Abstract In the frame of C-BORD
More informationInvestigation of Prompt Fission Neutron and Gamma Spectra with their covariance matrices. Application to 239 Pu+n th, 238 U+n 1.
Investigation of Prompt Fission Neutron and Gamma Spectra with their covariance matrices. Application to 239 Pu+n th, 238 U+n 1.8MeV, 235 U+n th O. Litaize, L. Berge, D. Regnier, O. Serot, Y. Peneliau,
More informationReactor radiation skyshine calculations with TRIPOLI-4 code for Baikal-1 experiments
DOI: 10.15669/pnst.4.303 Progress in Nuclear Science and Technology Volume 4 (2014) pp. 303-307 ARTICLE Reactor radiation skyshine calculations with code for Baikal-1 experiments Yi-Kang Lee * Commissariat
More informationAn introduction to Neutron Resonance Densitometry (Short Summary)
An introduction to Neutron Resonance Densitometry (Short Summary) H. Harada 1, M. Koizumi 1, H. Tsuchiya 1, F. Kitatani 1, M. Seya 1 B. Becker 2, J. Heyse 2, S. Kopecky 2, C. Paradela 2, P. Schillebeeckx
More informationDetection of explosives and fissile material based on neutron generators, survey of techniques and methods. M. Bruggeman
Detection of explosives and fissile material based on neutron generators, survey of techniques and methods M. Bruggeman TM neutron generators 1 Vienna, IAEA, 13-16 June, 2005 Contents Context Initiating
More informationRequirements on Neutron Detectors Alternative to He-3
Requirements on Neutron Detectors Alternative to He-3 Wolfgang Rosenstock and Olaf Schumann Fraunhofer INT, Euskirchen, Germany Department wolfgang.rosenstock@int.fraunhofer.de Neutron Detector Technologies
More informationCharacterization of Large Structures & Components
Structures & Components KEY BENEFITS Key Drivers: Lack of good knowledge about the position, the identification and the radiological specification of contamination on or inside large components. Significant
More informationA Proposal of Nuclear Materials Detection and Inspection Systems in Heavily Shielded Suspicious Objects by Non-destructive Manner.
Magic Maggiore Technical Reachback Workshop 15 min. (March 28-30, 2017, JRC Ispra, Italy) A Proposal of Nuclear Materials Detection and Inspection Systems in Heavily Shielded Suspicious Objects by Non-destructive
More informationNew methodology for source location and activity determination in preparation of repairing or decommissioning activities
New methodology for source location and activity determination in preparation of repairing or decommissioning activities Authors: H. TOUBON 1, B. NOHL 2, S. LEFEVRE 3, M. CHIRON 4, K. BOUDERGUI 1, P. PIN
More informationNuclear Reactions A Z. Radioactivity, Spontaneous Decay: Nuclear Reaction, Induced Process: x + X Y + y + Q Q > 0. Exothermic Endothermic
Radioactivity, Spontaneous Decay: Nuclear Reactions A Z 4 P D+ He + Q A 4 Z 2 Q > 0 Nuclear Reaction, Induced Process: x + X Y + y + Q Q = ( m + m m m ) c 2 x X Y y Q > 0 Q < 0 Exothermic Endothermic 2
More informationThe Use of Neutron Generators for the Detection of Illicit Materials in the Sea Transportation System
The Use of Neutron Generators for the Detection of Illicit Materials in the Sea Transportation System G. Nebbia 1), M. Lunardon 1), S. Moretto 1), S. Pesente 1), G. Viesti 1), A. Fontana 2), A. Zenoni
More informationPulsed Neutron Interrogation Test Assembly - PUNITA
Pulsed Neutron Interrogation Test Assembly - PUNITA Bent Pedersen Nuclear Security Unit Institute for Transuranium Elements - ITU Joint Research Centre presented at IPNDV WG3 meeting, 12-13 May 2016 JRC,
More informationGamma-Spectrum Generator
1st Advanced Training Course ITCM with NUCLEONICA, Karlsruhe, Germany, 22-24 April, 2009 1 Gamma-Spectrum Generator A.N. Berlizov ITU - Institute for Transuranium Elements Karlsruhe - Germany http://itu.jrc.ec.europa.eu/
More informationApplication of prompt gamma activation analysis with neutron beams for the detection and analysis of nuclear materials in containers
Application of prompt gamma activation analysis with neutron beams for the detection and analysis of nuclear materials in containers Zsolt Révay Institute of Isotopes, Budapest, Hungary Dept. of Nuclear
More informationCharacterization of 3D thermal neutron semiconductor detectors
Characterization of 3D thermal neutron semiconductor detectors J.Uher 1, C.Fröjdh 2, J.Jakůbek 1, C.Kenney 3, Z.Kohout 4, V.Linhart 1, S.Parker 5, S.Petersson 2, S.Pospíšil 1, G.Thungström 2 (1),, Czech
More informationDESIGN AND OPERATION OF THE COMBINED TECHNOLOGY AUTOMATED WASTE CHARACTERISATION SYSTEM
11-A-429-INMM DESIGN AND OPERATION OF THE COMBINED TECHNOLOGY AUTOMATED WASTE CHARACTERISATION SYSTEM ABSTRACT John A. Mason, Marc R. Looman and Robert A. Price ANTECH, A. N. Technology Ltd. Unit 6, Thames
More informationFAST NEUTRON MULTIPLICITY COUNTER
FAST NEUTRON MULTIPLICITY COUNTER Di Fulvio A. 1, Shin T. 1, Sosa C. 1, Tyler J. 1, Supic L. 1, Clarke S. 1, Pozzi S. 1, Chichester D. 2 1 Department of Nuclear Engineering and Radiological Science of
More informationDetermination of the boron content in polyethylene samples using the reactor Orphée
Determination of the boron content in polyethylene samples using the reactor Orphée F. Gunsing, A. Menelle CEA Saclay, F-91191 Gif-sur-Yvette, France O. Aberle European Organization for Nuclear Research
More informationCompton suppression spectrometry
Compton suppression spectrometry In gamma ray spectrometry performed with High-purity Germanium detectors (HpGe), the detection of low intensity gamma ray lines is complicated by the presence of Compton
More informationDetermination of the activity of radionuclides
BUREAU NATIONAL DE MÉTROLOGIE COMMISSARIAT À L'ÉNERGIE ATOMIQUE LABORATOIRE NATIONAL HENRI BECQUEREL Note technique LNHB/04-33 Determination of the activity of radionuclides contained in volume samples
More informationQuartz-Crystal Spectrometer for the Analysis of Plutonium K X-Rays
Quartz-Crystal Spectrometer for the Analysis of Plutonium K X-Rays Alison V. Goodsell, William S. Charlton alisong@tamu.edu, charlton@ne.tamu.edu Nuclear Security Science & Policy Institute Texas A&M University,
More informationNGN PhD Studentship Proposal
NGN PhD Studentship Proposal Note that proposals will be assessed against both the quality of the scientific content and of the proposed training experience. Proposed supervisors (lead first) Dr Laura
More informationDesign of an Integrated Inspection System For Detection of Explosive and Illicit Materials
Design of an Integrated Inspection System For Detection of Explosive and Illicit Materials IAEA 2 nd CRP Meeting, Mumbai, 12 16 November 2007 R. M. Megahid Nuclear Research Centre, Atomic Energy Authority
More informationUse of Imaging for Nuclear Material Control and Accountability
Use of Imaging for Nuclear Material Control and Accountability James A. Mullens, Paul A. Hausladen, Philip Bingham, Daniel E Archer, Brandon Grogan, John T Mihalczo Oak Ridge National Laboratory Abstract
More informationISO INTERNATIONAL STANDARD
INTERNATIONAL STANDARD ISO 14850-1 First edition 2004-05-15 Nuclear energy Waste-packages activity measurement Part 1: High-resolution gamma spectrometry in integral mode with open geometry Énergie nucléaire
More informationThe Use of Self-Induced XRF to Quantify the Pu Content in PWR Spent Nuclear Fuel
The Use of Self-Induced XRF to Quantify the Pu Content in PWR Spent Nuclear Fuel William S. Charlton, Daniel Strohmeyer, Alissa Stafford Texas A&M University, College Station, TX 77843-3133 USA Steve Saavedra
More informationGRAPHITE GAS REACTORS SLA1 & SLA2 : FROM SAMPLING STRATEGY TO WORKING CONDITIONS
Decomissioning & Waste Management Unit GRAPHITE GAS REACTORS SLA1 & SLA2 : FROM SAMPLING STRATEGY TO WORKING CONDITIONS Atoms for the future 27 th -30 th June 2016 Contact : Clémence WEILL clemence.weill@edf.fr
More informationCALIBRATION OF SCINTILLATION DETECTORS USING A DT GENERATOR Jarrod D. Edwards, Sara A. Pozzi, and John T. Mihalczo
CALIBRATION OF SCINTILLATION DETECTORS USING A DT GENERATOR Jarrod D. Edwards, Sara A. Pozzi, and John T. Mihalczo Oak Ridge National Laboratory Oak Ridge, TN 37831-6010 PO Box 2008 Ms6010 ABSTRACT The
More informationPrinciples and Applications of Neutron Based Inspection Techniques. Tsahi Gozani Rapiscan Laboratories 520Almanor Ave, Sunnyvale, CA
Principles and Applications of Neutron Based Inspection Techniques Tsahi Gozani Rapiscan Laboratories 520Almanor Ave, Sunnyvale, CA Presentation to the International Topical meeting on Nuclear Research
More informationWM2014 Conference, March 2 6, 2014, Phoenix, Arizona, USA
Determination of Components of Fuel Matrix in Water and in Bottom Slimes in the MR Reactor Ponds in NRC Kurchatov Institute 14038 Alexey Stepanov *, Iurii Simirskii *, Ilya Semin *, Anatoly Volkovich *
More informationFissile material experiments at the Device Assembly Facility
Fissile material experiments at the Device Assembly Facility CVT Workshop October 20, 2016 Michael Hamel 1, Pete Chapman 2, Michael Streicher 1 1 University of Michigan 2 North Carolina State University
More informationWM2013 Conference, February 24 28, 2013, Phoenix, Arizona, USA
The Underwater Spectrometric System Based on CZT Detector for Survey of the Bottom of MR Reactor Pool 13461 Victor Potapov, Alexey Safronov, Oleg Ivanov, Sergey Smirnov, Vyacheslav Stepanov National Research
More informationTime Correlation Measurements of Heavily Shielded Uranium Metal. Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831
Time Correlation Measurements of Heavily Shielded Uranium Metal J. M. Crye **, S. M. McConchie, J. T. Mihalczo, K. E. Pena **, and H. L. Hall ** ** University of Tennessee, 303A Pasqua Engineering Bldg.,
More informationRρ corresponds to the doublets counting
Some techniques applied for plutonium measurements in waste drums B. Autrusson, J.L. Dufour, P. Funk, T. Lambert, N. Pépin, B. Thaurel Institut de Protection et de Sûreté Nucléaire, BP 6, 92265 Fontenay-aux-Roses,
More informationIntroduction to Environmental Measurement Techniques Radioactivity. Dana Pittauer 1of 48
Introduction to Environmental Measurement Techniques 2016 Radioactivity Dana Pittauer (dpittauer@marum.de) 1of 48 Introduction Radioisotopes are of interest in environmental physics for several reasons:
More informationPartial Neutron Capture Cross Section Determination of 237 Np, 242
Partial Neutron Capture Cross Section Determination of 237 Np, 242 Pu and 241 Am using Cold Neutron Beams Christoph Genreith 1, Matthias Rossbach 1 1 Institute of Energy and Climate Research, IEK-6, Forschungszentrum
More informationCollimated LaBr 3 detector response function in radioactivity analysis of nuclear waste drums
Nuclear Science and Techniques 4 (13) 63 Collimated LaBr 3 detector response function in radioactivity analysis of nuclear waste drums QIAN Nan 1 WANG Dezhong 1,* WANG Chuan ZHU Yuelong MAUERHOFER Eric
More informationEmerging Capabilities for Advanced Nuclear Safeguards Measurement Solutions
Emerging Capabilities for Advanced Nuclear Safeguards Measurement Solutions Robert McElroy, Stephen Croft, Angela Lousteau, Ram Venkataraman, Presented at the Novel Technologies, Techniques, and Methods
More informationIAEA-SM-367/10/04/P SCREENING AND RADIOMETRIC MEASUREMENT OF ENVIRONMENTAL SWIPE SAMPLES
IAEA-SM-367/10/04/P SCREENING AND RADIOMETRIC MEASUREMENT OF ENVIRONMENTAL SWIPE SAMPLES V. MAIOROV, A. CIURAPINSKI, W. RAAB and V. JANSTA Safeguards Analytical Laboratory, International Atomic Energy
More informationEnvironmental Applications
Environmental Applications Gamma ray Spectrometry Paul Nolan University of Liverpool Gamma ray spectrometry of environmental samples is a standard technique Germanium detector Programs available for spectrum
More informationOriginal Paper Fission Gas Bubbles Characterisation in Irradiated UO 2 Fuel by SEM, EPMA and SIMS
Microchim Acta 155, 183 187 (2006) DOI 10.1007/s00604-006-0540-y Original Paper Fission Gas Bubbles Characterisation in Irradiated UO 2 Fuel by SEM, EPMA and SIMS Jérôme Lamontagne, Lionel Desgranges,
More informationDetection efficiency of a BEGe detector using the Monte Carlo method and a comparison to other calibration methods. Abstract
Detection efficiency of a BEGe detector using the Monte Carlo method and a comparison to other calibration methods N. Stefanakis 1 1 GMA Gamma measurements and analyses e.k. PO Box 1611, 72706 Reutlingen,
More informationHigh Precision Nondestructive Assay to Complement DA. H.O. Menlove, M.T. Swinhoe, and J.B. Marlow Los Alamos National Laboratory
High Precision Nondestructive Assay to Complement DA H.O. Menlove, M.T. Swinhoe, and J.B. Marlow Los Alamos National Laboratory LA-UR-07-6857 Abstract Large scale spent fuel reprocessing plants and fuel
More informationFast Neutron Multiplicity Counter: Development of an active-mode counter UM-INL Collaboration
Fast Neutron Multiplicity Counter: Development of an active-mode counter UM-INL Collaboration T.H. Shin 1, A. Di Fulvio 1, D.L. Chichester 2, S.D. Clarke 1, S.A. Pozzi 1 * thshin@umich.edu 1 Department
More informationPrototypes and fuel cycle options including transmutation
A S T R I D Prototypes and fuel cycle options including transmutation General introduction, GEN IV fast reactors Transmutation demonstration Fuel cycle Conclusions www.cea.fr DEN/CAD/DER/CPA Jean-Paul
More informationREFERENCE SOURCES FOR THE CALIBRATION OF THE AUTOCORRELATION SINGLE-CRYSTAL SCINTILLATION TIME SPECTROMETER
REFERENCE SOURCES FOR THE CALIBRATION OF THE AUTOCORRELATION SINGLE-CRYSTAL SCINTILLATION TIME SPECTROMETER V.A. MOROZOV 1, N.V. MOROZOVA 1, T. BĂDICĂ 2, D. DELEANU 2,3, D. GHIŢĂ 2, S. PASCU 2,3 1 Joint
More informationIMAGING BOXED WASTE ASSAY SYSTEM
IMAGING BOXED WASTE ASSAY SYSTEM (Text of Invited paper presented at the Emerging Technologies in Hazardous Waste Management V Meeting, Atlanta, Georgia, September 27-29, 1993.) John T. Caldwell, M. Andreatta,
More informationPrinciples of neutron TOF cross section measurements
Principles of neutron TOF cross section measurements J. Heyse, C. Paradela, P. Schillebeeckx EC JRC IRMM Standards for Nuclear Safety, Security and Safeguards (SN3S) H.I. Kim Korea Atomic Energy Research
More informationEvaluation of Nondestructive Assay Characterization Methods for Pipe- Over-Pack Containers
Evaluation of Nondestructive Assay Characterization Methods for Pipe- Over-Pack Containers S.B. Stanfield, J.R. Wachter, D.L. Cramer Canberra Instruments Inc. 800 Research Pkwy, Meriden, CT 06450 USA ABSTRACT
More informationVerification of fissile materials
Verification of fissile materials Naeem U. H. Syed, Alexander Bürger, Styrkaar Hustveit, Ole Reistad,Tonje Sekse GammaSem seminar 2010 28/09/2010-29/09/2010 Overview Introduction Background The Black Sea
More informationIPNDV Working Group 3: Technical Challenges and Solutions Nuclear Material (3) Technology Data Sheet
Nuclear Material (NM) Technology Name: Gamma-Ray Imaging Physical Principle/Methodology of Technology: Gamma-ray imaging provides the location and shape information of gamma-ray emitting radionuclides.
More informationA Germanium Detector with Optimized Compton Veto for High Sensitivity at Low Energy
LLNL-TR-518852 A Germanium Detector with Optimized Compton Veto for High Sensitivity at Low Energy S. Friedrich December 6, 2011 Disclaimer This document was prepared as an account of work sponsored by
More informationSeaborg s Plutonium?
Seaborg s Plutonium? Eric B. Norman, Keenan J. Thomas, Kristina E. Telhami* Department of Nuclear Engineering University of California Berkeley, CA 94720 Abstract Passive x-ray and gamma ray analysis was
More informationWM 05 Conference, February 27 - March 3, 2005, Tucson, AZ INTEGRATED WASTE ASSAY SYSTEM (IWAS) AND ANALYSIS ENHANCEMENTS
INTEGRATED WASTE ASSAY SYSTEM (IWAS) AND ANALYSIS ENHANCEMENTS R.D. McElroy, Jr. and S. Croft Canberra Industries, Inc. ABSTRACT The Integrated Waste Assay System (IWAS) is a hybrid waste assay system
More informationPoS(ICHEP2016)474. SoLid: Search for Oscillations with a Lithium-6 Detector at the SCK CEN BR2 reactor
SoLid: Search for Oscillations with a Lithium-6 Detector at the SCK CEN BR2 reactor University of Bristol E-mail: dan.saunders@bristol.ac.uk The disappearance of reactor antineutrinos into a new neutral
More information(Tandem Collimators for the Tangential GammaRay Spectrometer - KM6T-TC)
2009 Annual Report of the EURATOM-MEdC Association 188 Tandem Collimators System (Tandem Collimators for the Tangential GammaRay Spectrometer - KM6T-TC) S. Soare 1, T. Craciunescu 2, M. Curuia 1, V. Zoita
More informationSCANNING OF CARGO CONTAINERS BY GAMMA-RAY AND FAST NEUTRON RADIOGRAPHY
Armenian Journal of Physics, 2012, vol. 5, issue 1, pp. 1-7 SCANNING OF CARGO CONTAINERS BY GAMMA-RAY AND FAST NEUTRON RADIOGRAPHY A. M. Yousri*, A. M. Osman, W. A. Kansouh, A. M. Reda*, I. I. Bashter*,
More informationConsortium for Verification Technology
Advanced Safeguard Tools (Thrust Area #3) Zhong He University of Michigan 4 th Workshop, Michigan League, UM, Nov. 29 30, 2017 October 18, 2017 Nonproliferation Treaty Fissile Material Cutoff Treaty Develop
More informationINSTRUMENTAL TECHNIQUE FOR THE DETECTION AND IDENTIFICATION OF RADIOACTIVE, FISSILE AND EXTRA HAZARDOUS SUBSTANCES
17th World Conference on Nondestructive Testing, 25-28 Oct 2008, Shanghai, China INSTRUMENTAL TECHNIQUE FOR THE DETECTION AND IDENTIFICATION OF RADIOACTIVE, FISSILE AND EXTRA HAZARDOUS SUBSTANCES Nikolay
More informationNew perspectives in X-ray detection of concealed illicit materials brought by CdTe/CdZnTe spectrometric detectors
New perspectives in X-ray detection of concealed illicit materials brought by CdTe/CdZnTe spectrometric detectors Jean-Marc Dinten, Jean-Louis Amans, Loïck Verger, Olivier Peyret CEA-LETI, MINATEC, Recherche
More informationPete Burgess, Nuvia Limited. Clearance and exemption
Pete Burgess, Nuvia Limited Clearance and exemption The clearance, exclusion and exemption process Most of the UK nuclear industry (and many other organisations) refer to the Clearance and Exemption Working
More informationMCNP6 simulation validation of fast neutron coincidence detection system for nuclear security and safeguards applications
MCNP6 simulation validation of fast neutron coincidence detection system for nuclear security and safeguards applications Débora M. Trombetta 1, Bo Cederwall 1, Kåre Axell1 2 1 Department of Physics, KTH
More informationA new approach in the detection of weak γ-ray peak of the radioactive. waste in tomography γ scanning
A new approach in the detection of weak γ-ray peak of the radioactive waste in tomography γ scanning Zhang Jinzhao ( 张金钊 ), Tuo Xianguo,2,3 ( 庹先国 ) () Chengdu University of Technology Applied Nuclear Techniques
More informationWASTE DRUMS MEASUREMENTS
WASTE DRUMS MEASUREMENTS J.L. Dufour, B.Autrusson, P. Funk Institut de Radioprotection et de Sûreté Nucléaire-Radioactive Material Security Department B.P. 17-92262 Fontenay-Aux-Roses Cédex - France. 1.
More informationITU-Nuclear Safeguards and Security Unit
Development of measurement methods for nuclear materials (U/Pu) at enrichment and reprocessing facilities based on X-ray fluorescence, neutron coincidence counting and/or KX-ray absorption spectrometry
More informationStudies of the XENON100 Electromagnetic Background
Studies of the XENON100 Electromagnetic Background Daniel Mayani Physik-Institut University of Zurich PhD Seminar PSI, August 26-27, 2015 Searching for elusive particles The main challenge for experiments
More informationA New MCNPX PTRAC Coincidence Capture File Capability: A Tool for Neutron Detector Design
Abstract A New MCNPX PTRAC Coincidence Capture File Capability: A Tool for Neutron Detector Design L. G. Evans, M.A. Schear, J. S. Hendricks, M.T. Swinhoe, S.J. Tobin and S. Croft Los Alamos National Laboratory
More informationPhotoneutron Interrogation of Uranium Samples by a 4 MeV LINAC. A Feasibility Study
Photoneutron Interrogation of Uranium Samples by a 4 MeV LINAC. A Feasibility Study L. Lakosi, C. T. Nguyen, J. Bagi Institute of Isotopes, Hungarian Academy of Sciences P. O. Box 77, H-1525 Budapest,
More informationDevelopment of an active scintillating target for fission studies. J. Aupiais, G. Bélier CEA, DAM, DIF, F Arpajon France
Development of an active scintillating target for fission studies J. Aupiais, G. Bélier CEA, DAM, DIF, F-91297 Arpajon France 1 Motivations Fast neutron induced reactions are important for future nuclear
More informationEffect of Co-60 Single Escape Peak on Detection of Cs-137 in Analysis of Radionuclide from Research Reactor. Abstract
Organized and hosted by the Canadian Nuclear Society. Vancouver, BC, Canada. 2006 September 10-14 Effect of Co-60 Single Escape Peak on Detection of Cs-137 in Analysis of Radionuclide from Research Reactor
More informationProblem P7. Stéphanie Ménard. Dosimetry Department Fontenay-aux FRANCE IRSN QUADOS IRSN
Problem P7 Stéphanie Ménard Dosimetry Department 92262 Fontenay-aux aux-roses FRANCE What are the applications of Gamma-Ray Spectrometry in Radiological Protection and in Safety? In the environment: after
More informationNeutron emission asymmetries from linearly polarized γ rays on nat Cd, nat Sn, and 181 Ta
Neutron emission asymmetries from linearly polarized γ rays on nat Cd, nat Sn, and 8 Ta Clarke Smith, Gerald Feldman, and the HIγS Collaboration George Triangle C. Smith, G. Feldman (GWU) Washington University
More informationMeasurements of Neutron Total and Capture Cross Sections at the TOF spectrometers of the Moscow Meson Factory
Measurements of Neutron Total and Capture Cross Sections at the TOF spectrometers of the Moscow Meson Factory Yu.V. Grigoriev 1,2, D.V. Khlustin 1, Zh.V. Mezentseva 2, Yu.V. Ryabov 1 1 Institute for Nuclear
More informationControl of the fission chain reaction
Control of the fission chain reaction Introduction to Nuclear Science Simon Fraser University Spring 2011 NUCS 342 April 8, 2011 NUCS 342 (Lecture 30) April 8, 2011 1 / 29 Outline 1 Fission chain reaction
More informationIdentiFINDER Digital Hand Held Spectrometer & Dose Rate Meter for Portable Applications
fire IdentiFINDER Digital Hand Held Spectrometer & The world s smallest spectrometer and dose rate meter designed for portable applications. safety security identifinder - CH (yellow) CZT and neutron detector
More informationNeutron facilities and generation. Rob McQueeney, Ames Laboratory and Iowa State University
Neutron facilities and generation Rob McQueeney, Ames Laboratory and Iowa State University September 12, 2018 19-Sep-18 Physics 502 2 Neutrons compared to other probes of matter Bulk probe Interacts with
More informationCharacterization of radioactive waste and packages
Characterization of radioactive waste and packages Peter Ivanov Acoustics & Ionising Radiation National Physical Laboratory, UK IAEA WS RER9106/9009/01, Visaginas, Lithuania, 24-28 August 2015 Contents:
More informationGamma background measurements in the Boulby Underground Laboratory
J Radioanal Nucl Chem (2013) 298:1483 1489 DOI 10.1007/s10967-013-2540-9 Gamma background measurements in the Boulby Underground Laboratory Dariusz Malczewski Jan Kisiel Jerzy Dorda Received: 1 March 2013
More informationEffect of Cosmic-ray Shielding in Passive Neutron Coincidence Counting
Effect of Cosmic-ray Shielding in Passive Neutron Coincidence Counting E. Alvarez, C.G. Wilkins CANBERRA Harwell Ltd. B528.10 Unit 1, Harwell International Business Centre, Didcot, Oxfordshire, OX11 0TA
More informationInteractive Web Accessible Gamma-Spectrum Generator & EasyMonteCarlo Tools
10th Nuclear Science Training Course with NUCLEONICA, Cesme, Turkey, 8-10 October, 2008 1 Interactive Web Accessible Gamma-Spectrum Generator & EasyMonteCarlo Tools A.N. Berlizov ITU - Institute for Transuranium
More informationActivation Analysis. Characteristic decay mechanisms, α, β, γ Activity A reveals the abundance N:
2.5. Isotope analysis and neutron activation techniques The previously discussed techniques of material analysis are mainly based on the characteristic atomic structure of the elements and the associated
More informationActivities of the neutron standardization. at the Korea Research Institute of Standards and Science (KRISS)
Activities of the neutron standardization at the Korea Research Institute of Standards and Science (KRISS) I. Introduction The activities of neutron standardization in KRISS have been continued for last
More informationApplication of LaBr 3 detector for neutron resonance densitometry
Application of LaBr 3 detector for neutron resonance densitometry H. Tsuchiya 1, H. Harada 1, M. Koizumi 1, F. Kitatani 1, J. Takamine 1, M. Kureta 1, H. Iimura 1, B. Becker 2, S. Kopecky 2, P. Schillebeeckx
More informationG. Jossens a, C. Deyglun a, P. Gironès b, C. Mathonat a *, and A.Godot a
INMM 2015, NDA quantification of Nuclear Waste Containers G. Jossens a, C. Deyglun a, P. Gironès b, C. Mathonat a *, and A.Godot a a KEP Technologies SETARAM, 7 rue de l Oratoire, Caluire, 69300, France
More informationWM2014 Conference, March 2 6, 2014, Phoenix, Arizona, USA
Experimental Comparison between High Purity Germanium and Scintillator Detectors for Determining Burnup, Cooling Time and Decay Heat of Used Nuclear Fuel - 14488 Peter Jansson *, Sophie Grape *, Stephen
More information