Development of Self-Interrogation Neutron Resonance Densitometry to Quantify the Fissile Content in PWR Spent LEU and MOX Assemblies

Author:

LaFleur Adrienne M.1,Charlton William S.2,Menlove Howard O.1,Swinhoe Martyn T.1

Affiliation:

1. Nuclear Nonproliferation Division, Los Alamos National Laboratory P.O. Box 1663, MS E540, Los Alamos, New Mexico 87545

2. Nuclear Security Science and Policy Institute, Texas A&M University 3473 TAMU, College Station, Texas 77843

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Cited by 8 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Sensitivity simulation on isotopic fissile measurement using neutron resonances;Nuclear Engineering and Technology;2022-02

2. Spent fuel nondestructive assay integrated characterization from active neutron, passive neutron, and passive gamma;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2021-02

3. SINRD validation experiments at the time-of-flight facility GELINA;Annals of Nuclear Energy;2017-04

4. Neutron absorbers and detector types for spent fuel verification using the self-interrogation neutron resonance densitometry;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2015-08

5. Analysis of experimental measurements of PWR fresh and spent fuel assemblies using Self-Interrogation Neutron Resonance Densitometry;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2015-05

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