Validation of a Continuous-Energy Monte Carlo Burn-up Code MVP-BURN and Its Application to Analysis of Post Irradiation Experiment

By K. Okumura, Takamasa Mori, M. Nakagawa, K. Kaneko. 2000

148 citations recorded by the source corpus.

Subfields: Aerospace Engineering, Materials Chemistry, Radiation

View Paper: https://www.semanticscholar.org/paper/da6b4a913bc5da966197af5d5f5e14de71bb4991

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In Aerospace Engineering

1. J. Leppänen

In Materials Chemistry

1. J. Leppänen

In Radiation

1. J. Leppänen

Citations in the corpus

• Development of a New Monte Carlo reactor physics code (2007, methodology): “The standard version of MVP-BURN can be used for the calculation of homogenised reaction cross sections and assembly discontinuity factors.”
• MCCARD : MONTE CARLO CODE FOR ADVANCED REACTOR DESIGN AND ANALYSIS (2012, methodology): “Figures 3 and 4 compare the McCARD estimates on burnup dependent k inf with those from other computations by HELIOS [13], CASMO [38], and MVP-BURN [39] codes for the UO 2 fuel pin cell and FA problems, respectively.”