Total neutron emission generation and characterization for a Next Generation Safeguards Initiative spent fuel library

Author:

Weldon R.A.,Fensin M.L.,Trellue H.R.

Funder

Next Generation Safeguards Initiative

Office of Nonproliferation and International Security

National Nuclear Security Administration

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference20 articles.

1. Production of Actinide Isotopes in Simulated PWR Fuel and Their Influence on Inherent Neutron Emission;Bosler,1982

2. ORIGEN2-A Revised and Updated Version of the Oak Ridge Isotope Generation and Depletion Code;Croff,1980

3. A Monte Carlo Linked Depletion Spent Fuel Library for Assessing Varied Nondestructive Assay Techniques for Nuclear Safeguards;Fensin,2009

4. The enhancements and testing for the MCNPX 2.6.0 depletion capability;Fensin;J. Nucl. Technol.,2010

5. Determining the Pu Mass in LEU Spent Fuel Assemblies – Focus on Passive Gamma Detection;Fensin,2010

Cited by 3 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. 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

2. Computation of the neutron multiplicity moments for research reactor fuels using MCNP6 and SOURCES4c;International Journal of Energy Research;2019-08-22

3. Development of Neutron Energy Spectral Signatures for Passive Monitoring of Spent Nuclear Fuels in Dry Cask Storage;EPJ Web of Conferences;2018

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