Modeling the Detection of Delayed Neutron Signatures in MCNP6 and Comparisons with Measurements of 233U, 235U, and 239Pu

Author:

Andrews M. T.12,Goorley J. T.2,Corcoran E. C.1,Kelly D. G.1

Affiliation:

1. Royal Military College of Canada, P.O. Box 17000 Station Forces, Kingston, Ontario Canada K7K 7B4

2. Los Alamos National Laboratory, MS A143, Los Alamos, New Mexico 87545

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference8 articles.

1. “MCNPXTM User’s Manual Version 2.7.0,” LA-CP-11-00438, D. B. Pelowitz, Ed. Los Alamos National Laboratory (Apr. 2011).

2. R. J. Spaulding, “Design Fundamentals for Cost-Optimized Neutron Detectors Based on an Array of Helium-3 Tubes,” MS Thesis, Idaho State University (2009).

3. M. T. Sellers, “A Delayed Neutron Counting System for the Analysis of Special Nuclear Materials,” MASC Thesis, Royal Military College of Canada (2011).

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. MCNP6 simulations of gamma line emissions from fission products and their comparisons to plutonium and uranium measurements;Progress in Nuclear Energy;2015-03

2. A system for the measurement of delayed neutrons and gammas from special nuclear materials;Journal of Radioanalytical and Nuclear Chemistry;2014-11-27

3. Features of MCNP6;SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo;2014

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