Proposal of Direct Calculation of Kinetic Parameters β_<eff> and Λ Based on Continuous Energy Monte Carlo Method
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概要
- 論文の詳細を見る
Direct calculation methods of kinetic parameters are proposed based on the continuous energy Monte Carlo method. In the proposed methods, the effective delayed neutron fraction βeff and the neutron generation time Λ are estimated using eigenvalue calculations. The expected number of fission neutrons in the next generation is newly applied to the proposed methods instead of the adjoint flux that has been conventionally used. The algorithms to estimate the kinetic parameters are established and incorporated into the continuous energy Monte Carlo transport calculation code MCNP-4C, which is versatile for eigenvalue calculations of nuclear reactor cores with various types of neutron energy spectrum and geometry. The proposed methods were validated since the calculated values agreed with the experimental data of βeff and βeff⁄Λ for the critical cores within accuracies of 4.5% and 10%, respectively.
- 社団法人 日本原子力学会の論文
- 2005-06-25
著者
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Nauchi Yasushi
Central Research Institute Of Electric Power Industry
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Kameyama Takanori
Central Research Institute of Electric Power Industry
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Kameyama Takanori
Central Res. Inst. Of Electric Power Ind.
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Nauchi Yasushi
Central Res. Inst. Of Electric Power Ind.
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