Development of Calculation Technique for Iterated Fission Probability and Reactor Kinetic Parameters Using Continuous-Energy Monte Carlo Method

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概要

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• New algorithms and techniques are developed for calculating the iterated fission probability (IFP) using a Monte Carlo eigenvalue calculation scheme. The proportionality of the calculated IFP to the adjoint flux is confirmed numerically. This IFP is then used with the MCNP code and its point-wise cross section data libraries to calculate kinetic parameters weighted by the adjoint flux. Experimental data for critical cores validate these theoretical estimates.

• 社団法人 日本原子力学会の論文

著者

• Nauchi Yasushi

  Central Research Institute Of Electric Power Industry

• Kameyama Takanori

  Central Research Institute of Electric Power Industry

関連論文

• Development of Calculation Technique for Iterated Fission Probability and Reactor Kinetic Parameters Using Continuous-Energy Monte Carlo Method
• Analyses of Burnup at plutonium Spots in Uranium-Plutonium Mixed Oxide Fuels in Light Water Reactors by Neutron Transport and Burnup Calculations
• Development of Calculation Technique for Iterated Fission Probability and Reactor Kinetic Parameters Using Continuous-Energy Monte Carlo Method
• Proposal of Direct Calculation of Kinetic Parameters β_ and Λ Based on Continuous Energy Monte Carlo Method

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