Validity of the Monte Carlo Method for Shielding Analysis of a Spent-Fuel Shipping Cask: Comparison with Experiment-Reference-Cited by-同舟云学术

Validity of the Monte Carlo Method for Shielding Analysis of a Spent-Fuel Shipping Cask: Comparison with Experiment

Published:1983-07 Issue:3 Volume:84 Page:271-284
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Ueki K.¹,Inoue M.²,Maki Y.²

Affiliation:

1. Ship Research Institute, Nuclear Ship Division, 6-38-1 Shinkawa, Mitaka, Tokyo 181, Japan

2. Central Research Institute of Electric Power Industry, Structure Department, Civil Engineering Laboratory, 1646 Abiko, Abiko, Ibaraki 270-11, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE83-A17795

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1. Study of the Site Dose Rate for the ISFSI Facility with Monte Carlo and Deterministic Methods;Nuclear Technology;2009-10

2. Application of Biasing Optimization Techniques to Monte Carlo Shielding Analysis of a Transport Cask;Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications;2001

3. CONTINUOUS ENERGY MONTE-CARLO ANALYSIS OF NEUTRON SHIELDING BENCHMARK EXPERIMENTS WITH CROSS-SECTIONS IN JENDL-3;J NUCL SCI TECHNOL;1993

4. Continuous Energy Monte Carlo Analysis of Neutron Shielding Benchmark Experiments with Cross Sections in JENDL-3;Journal of Nuclear Science and Technology;1993-04

5. Application of the Monte Carlo Method for Neutron Shielding Analysis of Transport Casks;International Journal of Radioactive Materials Transport;1990-01