Characterization and performance evaluation of a new passive neutron albedo reactivity counter for safeguards measurements |
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| Institution: | 1. Nuclear Engineering & Nonproliferation Division, Los Alamos National Laboratory, P.O. Box 1663 MS E540, Los Alamos, NM 87545-0001, USA;2. Korea Atomic Energy Research Institute, 1045 Daedeok, Yuseong-gu, Daejeon 305-353, Republic of Korea;1. G.W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA 30332, USA;2. School of Civil and Environmental Engineering, Georgia Institute of Technology, Atlanta, GA 30332, USA;3. Electric Power Research Institute, Charlotte, NC 28262, USA;4. Korea Atomic Energy Research Institute, Daeduk, Taejon 305-353, South Korea;1. Japan Atomic Energy Agency, Naka, Japan;2. Korea Atomic Energy Research Institute, Daejeon, Republic of Korea;3. National Fusion Research Institute, Daejeon, Republic of Korea;1. National Fusion Research Institute, Daejeon, Republic of Korea;2. Korea Atomic Energy Research Institute, Daejeon, Republic of Korea |
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| Abstract: | A prototype 3He-based Passive Neutron Albedo Reactivity (PNAR) counter was developed and tested at Los Alamos National Laboratory (LANL) in collaboration with the Korea Atomic Energy Research Institute (KAERI) to measure the fissile content in electrochemical recycling (ER) product materials. The counter consists of 16 3He cylindrical gas-filled proportional counters at 4 atm of pressure embedded in high-density polyethylene. In this work, experimental measurements were performed at LANL to characterize the performance of the PNAR counter using surrogate materials for the uranium metal ingot. The purpose of these experiments was to: 1) measure the operating and calibration parameters of the PNAR counter (e.g. efficiency profiles, coincidence gate fractions, die-away time) and 2) evaluate the accuracy and sensitivity of the PNAR method and the time correlated induced fission (TCIF) method for quantifying the 235U mass in PWR fresh LEU fuel rods and Materials Testing Reactor (MTR) HEU fuel plates. A small 244Cm reference source (13,373 n/s) was placed in the center of the fuel rods and fuel plates to simulate spontaneous fission from sub-ppm (parts per million) levels of Cm contamination in the U ingot. In order to compare the relative accuracy of the PNAR and TCIF methods for quantifying 235U mass, calibration curves were generated for the net doubles rate and the doubles Cd ratio using the Deming software. The results from this experiment will be used to obtain a better understanding of the sensitivity of the PNAR and TCIF methods for samples with low neutron multiplication. Furthermore, this experimental measurement data will also help inform safeguards research and development (R&D) efforts on the viability of nondestructive assay (NDA) techniques and detector designs for quantifying fissile content in ER product materials. Future work will include performing measurements with the PNAR counter on small samples of U/TRU materials. |
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| Keywords: | Nuclear safeguards Neutron detector Non-destructive assay |
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