Research on Method of Generating Monte Carlo Multigroup Library for Fast Reactor

被引：0

作者：

Zhu S. ^{[1
]}

Ma X. ^{[1
]}

Xu Q. ^{[1
]}

Cao B. ^{[1
]}

Chen Y. ^{[1
]}

机构：

[1] School of Nuclear Science and Engineering, North China Electric Power University, Beijing

来源：

Ma, Xubo (maxb917@163.com) | 1600年 / Atomic Energy Press卷 / 41期

关键词：

Criticality calculation; MGXSMC; Monte Carlo multigroup library; Scattering cross section;

D O I：

10.13832/j.jnpe.2020.05.0035

中图分类号：

学科分类号：

摘要：

Based on the discrete angle method, a Monte Carlo multi-group cross section generation program MGXSMC was developed. This program can read the cross section data from an input file or read the cross section from a library in a specified format to generate the multi-group cross section for MCNP or RMC. The corresponding index file list can be automatically generated. The two-dimensional two-group IAEA pressurized water reactor (PWR) benchmark and lead-based fast reactor (RBEC-M) benchmark were used to verify the cross section library generated by the MGXSMC program. The calculation results show that the difference between the calculated result of the P5 order approximate multigroup section and the continuous point cross section is 24 pcm (1pcm = 10-5), and the difference of the keff result calculated by the P0 order approximate multigroup section and the continuous point section is large. This shows that the method and the program developed for the Monte Carlo Group Section Library are correct. At the same time, the neutron anisotropic scattering has a large impact on the calculation results of the lead-based fast reactor. Therefore, when the Monte Carlo Group Section library is produced, the neutron scattering angle data should be added. © 2020, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.

引用

页码：35 / 39

页数：4

共 10 条

[1] WANG K, LI Z G, SHE D, Et al., Progress on RMC: a Monte Carlo neutron transport code for reactor analysis, Rio de Janeiro: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, (2011)
[2] 1
[3] HU L Q, LONG P C, SONG J, Et al., SuperMC cloud for nuclear design and safety evaluation, Annals of Nuclear Energy, 134, 1, pp. 424-431, (2019)
[4] WAGNER J C, REDMOND E L, PALMTAG S P, Et al., MCNP: Multigroup/adjoint capabilities: LA-12704, (1994)
[5] YANG W S., Fast reactor physics and computational methods, Nuclear Engineering and Technology, 44, 2, pp. 177-198, (2012)
[6] DENG L, XIE Z S, ZHANG J M., MCGC: A 3-D multigroup P3 Monte Carlo code and its benchmarks, Journal of Nuclear Science and Technology, 37, 7, pp. 608-614, (2000)
[7] 8
[8] CHAO Y A, SHATILLA Y A., Conformal mapping and hexagonal nodal methods-II: implementation in the ANC-H code, Nuclear Science and Engineering, 121, 2, pp. 210-225, (1995)
[9] QIU R M, MA X B, XU Q, Et al., Development and verification of multi-group cross section process code TXMAT for fast reactor RBEC-M analysis, (2017)
[10] SIENICKI J J, MOISSEYTSEV A, YANG W S, Et al., Status report on the small secure transportable autonomous reactor(SSTAR)/lead-cooled fast reactor (LFR) and supporting research and development: ANL-GenIV-089, (2008)

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