Review of Hybrid Methods for Deep-Penetration Neutron Transport

被引:29
作者
Munk, Madicken [1 ]
Slaybaugh, Rachel N. [2 ]
机构
[1] Univ Illinois, Urbana Champaign Natl Ctr Supercomp Applicat, 1205 West Clark St,MC 257, Urbana, IL 61801 USA
[2] Univ Calif Berkeley, Nucl Engn Dept, 4155 Etcheverry Hall,MC 1730, Berkeley, CA 94720 USA
关键词
Neutron transport; hybrid methods; review; deep-penetration neutron transport; variance reduction; IMPORTANCE FUNCTION TRANSFORM; AUTOMATIC VARIANCE REDUCTION; CARLO SHIELDING CALCULATIONS; INFORMATION-THEORY; MONTE; SIMULATIONS; ADJOINT; ANGLE; CODE;
D O I
10.1080/00295639.2019.1586273
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
Methods for deep-penetration radiation transport remain important for radiation shielding, nonproliferation, nuclear threat reduction, and medical applications. As these applications become more ubiquitous, the need for accurate and reliable transport methods appropriate for these systems persists. For such systems, hybrid methods often obtain reliable answers in the shortest time by leveraging the speed and uniform uncertainty distribution of a deterministic solution to bias Monte Carlo transport and reduce the variance in the solution. This work reviews the state of the art among such hybrid methods. First, we summarize variance reduction (VR) for Monte Carlo radiation transport and existing efforts to automate these techniques. Relations among VR, importance, and the adjoint solution of the neutron transport equation are then discussed. Based on this exposition, the work transitions from theory to a critical review of existing VR implementations in modern nuclear engineering software. At present, the Consistent Adjoint-Driven Importance Sampling (CADIS) and Forward-Weighted Consistent Adjoint-Driven Importance Sampling (FW-CADIS) hybrid methods are the gold standard by which to reduce the variance in problems that have deeply penetrating radiation. The CADIS and FW-CADIS methods use an adjoint scalar flux to generate VR parameters for Monte Carlo radiation transport. Additionally, efforts to incorporate angular information into VR methods for Monte Carlo are summarized. Finally, we assess various implementations of these methods and the degree to which they improve VR for their target applications.
引用
收藏
页码:1055 / 1089
页数:35
相关论文
共 81 条
[51]  
REARDEN B. T., 2016, ORNL/TM-2005/39, Version 6.2.1
[52]  
ROWLAND K., 2018, THESIS
[53]   Assessment of the Lagrange Discrete Ordinates Equations for Three-Dimensional Neutron Transport [J].
Rowland, Kelly L. ;
Ahrens, Cory D. ;
Hamilton, Steven ;
Slaybaugh, R. N. .
NUCLEAR SCIENCE AND ENGINEERING, 2019, 193 (03) :233-252
[54]  
SEYDALIEV M., 2008, CONTRIBUTON THEORY S
[55]   DOSE EVALUATION FOR AN INDEPENDENT SPENT-FUEL STORAGE INSTALLATION USING MAVRIC [J].
Sheu, R. J. ;
Chen, Y. F. ;
Jiang, S. H. ;
Wang, J. N. ;
Lin, U. T. .
NUCLEAR TECHNOLOGY, 2011, 175 (01) :335-342
[56]  
Solomon CJ, 2014, NUCL SCI ENG, V176, P1
[57]  
SOMASUNDARAM E., 2013, P INT C MATH COMP ME
[58]   Automated variance reduction for MCNP using deterministic methods [J].
Sweezy, J ;
Brown, F ;
Booth, T ;
Chiaramonte, J ;
Preeg, B .
RADIATION PROTECTION DOSIMETRY, 2005, 116 (1-4) :508-512
[59]   MONTE-CARLO SHIELDING ANALYSES USING AN AUTOMATED BIASING PROCEDURE [J].
TANG, JS ;
HOFFMAN, TJ .
NUCLEAR SCIENCE AND ENGINEERING, 1988, 99 (04) :329-342
[60]   Automatic variance reduction for three-dimensional Monte Carlo simulations by the local importance function transform .1. Analysis [J].
Turner, SA ;
Larsen, EW .
NUCLEAR SCIENCE AND ENGINEERING, 1997, 127 (01) :22-35