Shielding Calculations for a Spent Fuel Storage Cask: A Comparison of Discrete Ordinates, Monte Carlo, and Hybrid Methods-Reference-Cited by-同舟云学术

Shielding Calculations for a Spent Fuel Storage Cask: A Comparison of Discrete Ordinates, Monte Carlo, and Hybrid Methods

Published:2008-05 Issue:1 Volume:159 Page:23-36
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Sheu R. J.¹,Chen A. Y.²,Liu Y.-W. H.²,Jiang S. H.²

Affiliation:

1. National Synchrotron Radiation Research Center 101 Hsin-Ann Road, Hsinchu Science Park, Hsinchu 300, Taiwan

2. National Tsing-Hua University Department of Engineering and System Science, Hsinchu 300, Taiwan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE159-23

Reference16 articles.

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2. Automated Variance Reduction of Monte Carlo Shielding Calculations Using the Discrete Ordinates Adjoint Function

3. X-5 MONTE CARLO TEAM, “MCNP—A General Purpose Monte Carlo N-Particle Transport Code, Version 5,” LAUR-03-1987, Los Alamos National Laboratory (2003).

4. J. C. WAGNER and A. HAGHIGHAT, “A3MCNP: Automated Adjoint Accelerated MCNP. User’s Manual, Version 1.0i,” H&S Advanced Computing Technologies Corporation (2000).

5. W. A. RHOADES and D. B. SIMPSON, “The TORT Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code,” ORNL/TM-13221, Oak Ridge National Laboratory (1997).

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