OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development

被引：10

作者：

Romano, Paul K. ^{[1
]}

Horelik, Nicholas E. ^{[1
]}

Herman, Bryan R. ^{[1
]}

Nelson, Adam G. ^{[2
]}

Forget, Benoit ^{[1
]}

Smith, Kord ^{[1
]}

机构：

[1] MIT, Dept Nucl Sci & Engn, 77 Massachusetts Ave, Cambridge, MA 02139 USA

[2] Univ Michigan, Dept Nucl Engn & Radiol Sci, 2355 Bonisteel Blvd, Ann Arbor, MI 48104 USA

来源：

SNA + MC 2013 - JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO | 2014年

关键词：

Monte Carlo; neutron transport; OpenMC; parallel; XML; HDF5; ALGORITHMS;

D O I：

10.1051/snamc/201406016

中图分类号：

TP39 [计算机的应用];

学科分类号：

081203 ; 0835 ;

摘要：

This paper gives an overview of OpenMC, an open source Monte Carlo particle transport code recently developed at the Massachusetts Institute of Technology. OpenMC uses continuous-energy cross sections and a constructive solid geometry representation, enabling high-fidelity modeling of nuclear reactors and other systems. Modern, portable input/output file formats are used in OpenMC: XML for input, and HDF5 for output. High performance parallel algorithms in OpenMC have demonstrated near-linear scaling to over 100,000 processors on modern supercomputers. Other topics discussed in this paper include plotting, CMFD acceleration, variance reduction, eigenvalue calculations, and software development processes.

引用

页数：8

共 50 条

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