Improvement of Monte Carlo Lattice Burnup Calculation Performance with the Correlated Sampling Method
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概要
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For next generation reactor designs, which are attempting wide variations of assembly configurations, the flexibility Monte Carlo method holds is attractive, but still costly for repetitive design study works. This paper presents an advanced correlated sampling (ACS) method which was developed to speed up Monte Carlo lattice burnup calculations. The ACS method is the combination of the correlated sampling method and a pseudo-scattering technique. All burnup steps are considered as consecutive perturbed problems using the same neutron collision history, which is pre-calculated based on a selected unperturbed problem. Since neutron weights can be adjusted on every collision point, rather than along paths between them, the perturbed calculation is very fast and the neutron collision history is light enough to be stored in memory or physical storage, which is an indispensable feature for consecutive perturbed calculations. The presented theory shows that the ACS method has good potential to work for a wide range of neutron absorption variations, the dominant perturbation in the lattice burnup. In an example calculation on a BWR lattice, the ACS calculation results of 600,000 neutrons/step agree well with the independent Monte Carlo runs of 20,000,000 neutrons/step within 0.1%dk⁄k in terms of k∞ throughout 95 steps (∼50 GWd/t). Average calculation time of neutron tracking with the former method is 3.4 s/step with 600,000 neutron histories on a single processor of an Alpha21164-600 MHz, and the speed-up factor against the Monte Carlo calculation turns out to be about 100.
- 一般社団法人 日本原子力学会の論文
- 2002-06-25
著者
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Aoyama Motoo
Power & Industrial Systems R & D Laboratory Hitachi Ltd.
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Aoyama Motoo
Power & Industrial Systems R & D Division Hitachi Ltd.
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MORIWAKI Masanao
Power & Industrial Systems R&D Laboratory, Hitachi, Ltd.
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Moriwaki Masanao
Power & Industrial Systems R & D Laboratory Hitachi Ltd.
関連論文
- A New Direct Calculation Method of Response Matrices Using a Monte Carlo Calculation
- Minor Actinide Transmutation in BWR Cores for Multi-recycle Operation with Less Minor Actinide-to-Fissile Plutonium Amount Ratio
- Multi-Assembly Analysis with an Advanced Correlated Sampling Method
- Improvement of Monte Carlo Lattice Burnup Calculation Performance with the Correlated Sampling Method