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Nuclear Technology Volume 175, 2011 - Issue 1: Special Issue on The 16th Biennial Topical Meeting of The Radiation Protection and Shielding Division
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Technical Paper

Dose Evaluation for an Independent Spent-Fuel Storage Installation Using MAVRIC

R. J. SheuNational Synchrotron Radiation Research Center, Hsinchu Science Park Hsinchu, Taiwan
,
Y. F. ChenNational Tsing Hua University, Department of Engineering and System Science Hsinchu, Taiwan
,
S. H. JiangNational Tsing Hua University, Department of Engineering and System Science Hsinchu, Taiwan;National Tsing Hua University, Institute of Nuclear Engineering and Science Hsinchu, Taiwan
,
J. N. WangInstitute of Nuclear Energy Research, Taoyuan 325, Taiwan
&
U. T. LinInstitute of Nuclear Energy Research, Taoyuan 325, Taiwan
Pages 335-342 | Published online: 10 Apr 2017

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P. C. Lai & R. J. Sheu. (2022) Separation of Flux/Dose Contributions from Multiple Transport Pathways in Monte Carlo Shielding Analyses of a Consolidated Interim Spent Nuclear Fuel Storage Facility. Nuclear Technology 208:4, pages 723-734.
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Madicken Munk & Rachel N. Slaybaugh. (2019) Review of Hybrid Methods for Deep-Penetration Neutron Transport. Nuclear Science and Engineering 193:10, pages 1055-1089.
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John C. Wagner, Douglas E. Peplow & Scott W. Mosher. (2014) FW-CADIS Method for Global and Regional Variance Reduction of Monte Carlo Radiation Transport Calculations. Nuclear Science and Engineering 176:1, pages 37-57.
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