Monte Carlo Methods, Models, and Applications to the Advanced Neutron Source-Reference-Cited by-同舟云学术

Monte Carlo Methods, Models, and Applications to the Advanced Neutron Source

Published:1991-09 Issue:3 Volume:95 Page:272-286
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Redmond Everett L.¹,Ryskamp John M.¹

Affiliation:

1. Idaho National Engineering Laboratory, EG&G Idaho, Inc., P.O. Box 1625, Idaho Falls, Idaho 83415

Publisher

Informa UK Limited

Subject

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

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT91-A34577

Reference14 articles.

1. Reactor Design of the Advanced Neutron Source

2. D. L. SELBY, R. M. HARRINGTON, and F. J. PERETZ, “Advanced Neutron Source Progress Report,” ORNL-6574, Oak Ridge National Laboratory (1990).

3. “MCNP—A General Monte Carlo Code for Neutron and Photon Transport (Version 3A),” LA-7396-M, Rev. 2, Los Alamos National Laboratory (1986).

4. E. L. REDMOND II, “Monte Carlo Methods, Models, and Applications for the Advanced Neutron Source,” MS Thesis, Massachusetts Institute of Technology (1990).

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