Development of neutron-photon coupling transport code IMPC-NP and optimization of method for fabrication of neutron-photon multi-group cross section

被引：1
|
作者：
Fang, Peng [1 ,2 ,3 ]
Wu, Xiang [1 ,2 ,3 ]
Lai, Hanghui [1 ,2 ,3 ]
Yang, Yongwei [1 ,2 ,3 ]
Yang, Lei [1 ,2 ,3 ]
Guo, Yuyao [1 ,2 ,3 ]
Zhou, Feng [3 ]
Zhu, Yanling [3 ]
机构：
[1] Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China
[2] Univ Chinese Acad Sci, Sch Nucl Sci & Technol, Beijing 100049, Peoples R China
[3] Adv Energy Sci & Technol Guangdong Lab, Huizhou 516000, Peoples R China
来源：
PROGRESS IN NUCLEAR ENERGY | 2024年 / 175卷
关键词：
Monte Carlo; Neutron -photon coupling transport; Fabrication of photon multi -group cross sec; tions; Scattering merging; DELTA-TRACKING; REACTOR;
D O I：
10.1016/j.pnucene.2024.105338
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
This paper introduces a Monte Carlo code IMPC-NP which can realize the simulation of neutron -photon coupling transport. In IMPC-NP, Delta -tracking algorithm and Weight delta -tracking algorithm are used for neutron and photon transport. A new method of fabrication of photon multi -group cross sections named "Scattering merging" is proposed, which is implemented and on IMPC-NP. The results of multiple benchmarks show that the new method can greatly improve the accuracy of neutron and photon calculation in deterministic code.
引用
收藏
页数：12
相关论文
共 16 条
  • [1] Verification of the Neutron-Photon multi-group Cross-Section library generated by Monte Carlo method code IMPC-NP
    Zhou, Feng
    Zhang, Teng
    Fang, Peng
    Yang, Yongwei
    Wu, Xiang
    Zhu, Yanling
    Liang, Qiuying
    Du, Shijie
    Ma, Xubo
    Yang, Lei
    NUCLEAR ENGINEERING AND DESIGN, 2025, 432
  • [2] NEUTRON-PHOTON MULTI-GROUP CROSS-SECTIONS FOR NEUTRON ENERGIES LESS-THAN-OR-EQUAL-TO 400 MEV
    ALSMILLER, RG
    BARISH, J
    NUCLEAR SCIENCE AND ENGINEERING, 1982, 80 (03) : 448 - 480
  • [3] Research and development of the neutron-photon coupled transport method in the fast reactor code system MOSASAUR
    Zhao, Chen
    Hu, Kui
    Wang, Lianjie
    Zhang, Bin
    Lou, Lei
    Lu, Di
    Ma, Xubo
    PROGRESS IN NUCLEAR ENERGY, 2024, 175
  • [4] Validation of coupled neutron-photon transport mode of Monte Carlo code MCS
    Lemaire, Matthieu
    Setiawan, Fathurrahman
    Lee, Hyunsuk
    Zhang, Peng
    Lee, Deokjung
    International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, 2019, : 588 - 597
  • [5] Development of a new parallel SN code for neutron-photon transport calculation in 3-D cylindrical geometry
    Xu, Longfei
    Cao, Liangzhi
    Zheng, Youqi
    Wu, Hongchun
    PROGRESS IN NUCLEAR ENERGY, 2017, 94 : 1 - 21
  • [6] Improved algorithms and coupled neutron-photon transport for auto-importance sampling method
    Wang, Xin
    Li, Jun-Li
    Wu, Zhen
    Qiu, Rui
    Li, Chun-Yan
    Liang, Man-Chun
    Zhang, Hui
    Gang, Zhi
    Xu, Hong
    CHINESE PHYSICS C, 2017, 41 (01)
  • [7] Improved algorithms and coupled neutron-photon transport for auto-importance sampling method
    王鑫
    李君利
    武祯
    邱睿
    李春艳
    梁漫春
    张辉
    刚直
    徐红
    Chinese Physics C, 2017, (01) : 104 - 113
  • [8] Development and verification of neutron and photon multi-group cross sections processing code TXMAT2.0
    Zhang, Bin
    Ma, Xubo
    Hu, Kui
    Zhou, Feng
    Chang, Changcheng
    Chen, Yixue
    PROGRESS IN NUCLEAR ENERGY, 2021, 138
  • [9] Simulation of full-core pin-by-pin model by JMCT Monte Carlo neutron-photon transport code
    Deng, Li
    Li, Gang
    Zhang, Bao-Yin
    Shangguan, Dan-Hua
    Li, Shu
    Hu, Ze-Hua
    Ma, Yan
    Ji, Zhi-Cheng
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2014, 48 (06): : 1061 - 1066
  • [10] The coupled neutron transport calculation of Monte Carlo multi-group and continuous cross section
    Deng, Li
    Hu, Zehua
    Li, Rui
    Cheng, Tangpei
    Yang, Chao
    Fu, Yuangang
    Shi, Dunfu
    Li, Gang
    Zhang, Baoyin
    Zhang, Lingyu
    Wen, Lili
    ANNALS OF NUCLEAR ENERGY, 2019, 127 : 433 - 436
12