Validation of a Continuous-Energy Monte Carlo Burn-up Code MVP-BURN and Its Application to Analysis of Post Irradiation Experiment
Author:
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://www.tandfonline.com/doi/pdf/10.1080/18811248.2000.9714876
Reference25 articles.
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2. Analyses of Burnup at Plutonium Spots in Uranium-Plutonium Mixed Oxide Fuels in Light Water Reactors by Neutron Transport and Burnup Calculations
3. Vectorization of Continuous Energy Monte Carlo Method for Neutron Transport Calculation
4. Mori , T. and Nakagawa , M. 1994.JAERI-Data/Code94–007. [in Japanese]
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