A hybrid Monte Carlo-Deterministic method for global particle transport calculations

被引:17
|
作者
Becker, Troy L. [1 ]
Wollaber, Allan B. [1 ]
Larsen, Edward W. [1 ]
机构
[1] Univ Michigan, Dept Nucl Engn & Radiol Sci, Ann Arbor, MI 48109 USA
关键词
D O I
10.13182/NSE07-A2653
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
A new hybrid Monte Carlo-Deterministic technique is presented for simulating global particle transport problems, in which flux estimates are desired at all physical locations in the system. This technique has two steps: First, an inexpensive deterministic global estimate of the forward flux is obtained; then Monte Carlo is used to estimate the multiplicative correction to the deterministic flux estimate. We call the multiplicative correction to the deterministic flux the correcton flux, and the Monte Carlo particles that estimate this flux correctons. For deep-penetration problems, the correcton flux has significantly less spatial variation than the physical flux. Therefore, the Monte Carlo process automatically distributes correctons much more uniformly across the system than it distributes Monte Carlo particles for the original angular flux. In the "deep" parts of the problem, at locations far from the source, this results in a greatly reduced variance and a greatly increased figure of merit.
引用
收藏
页码:155 / 167
页数:13
相关论文
共 50 条
  • [1] HYBRID MONTE CARLO-DETERMINISTIC METHODS FOR REACTOR ANALYSIS
    Wu, Zeyun
    Zhang, Qiong
    Abdel-Khalik, Hany
    NUCLEAR TECHNOLOGY, 2012, 180 (03) : 372 - 382
  • [2] DEVELOPMENT OF SUBSPACE-BASED HYBRID MONTE CARLO-DETERMINISTIC ALGORITHMS FOR REACTOR PHYSICS CALCULATIONS
    Zhang, Qiong
    Abdel-Khalik, Hany
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 6, 2014,
  • [3] Hybrid Monte Carlo-deterministic method for 3D neutron transport simulation based on energy region division
    Zhuang, Sixuan
    He, Peng
    Sun, Guangyao
    Hao, Lijuan
    Wu, Yican
    ANNALS OF NUCLEAR ENERGY, 2019, 130 : 271 - 276
  • [4] Automated weight windows for global Monte Carlo particle transport calculations
    Cooper, MA
    Larsen, EW
    NUCLEAR SCIENCE AND ENGINEERING, 2001, 137 (01) : 1 - 13
  • [5] Coupled Monte Carlo-Deterministic simulation of thermal behavior of graphene on substrate
    Coco, Marco
    INTERNATIONAL JOURNAL OF MODERN PHYSICS B, 2023, 37 (31):
  • [6] Assessment of uncertainties in Monte Carlo particle transport calculations
    Siebert, BRL
    PROCEEDINGS OF THE WORKSHOP "MONTE CARLO METHODS AND MODELS FOR APPLICATIONS IN ENERGY AND TECHNOLOGY", 1999, 6266 : 81 - +
  • [7] Natural radioactivity in building materials: dose determination in dwellings using hybrid Monte Carlo-deterministic approach
    Anjum, M. Zeeshan
    Mirza, Sikander M.
    Tufail, M.
    Mirza, Nasir M.
    Yasin, Zafar
    INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, VOL 2, PROCEEDINGS, 2008, : 941 - +
  • [8] Global variance reduction method for global Monte Carlo particle transport simulations of CFETR
    Nie, Xing-Chen
    Li, Jia
    Liu, Song-Lin
    Zhang, Xiao-Kang
    Zhao, Ping-Hui
    Ye, Min-You
    Vogel, German
    Yang, Xiao
    Zhu, Qing-Jun
    NUCLEAR SCIENCE AND TECHNIQUES, 2017, 28 (08)
  • [9] Global variance reduction method for global Monte Carlo particle transport simulations of CFETR
    Xing-Chen Nie
    Jia Li
    Song-Lin Liu
    Xiao-Kang Zhang
    Ping-Hui Zhao
    Min-You Ye
    German Vogel
    Xiao Yang
    Qing-Jun Zhu
    NuclearScienceandTechniques, 2017, 28 (08) : 127 - 133
  • [10] Global variance reduction method for global Monte Carlo particle transport simulations of CFETR
    Xing-Chen Nie
    Jia Li
    Song-Lin Liu
    Xiao-Kang Zhang
    Ping-Hui Zhao
    Min-You Ye
    German Vogel
    Xiao Yang
    Qing-Jun Zhu
    Nuclear Science and Techniques, 2017, 28