M
Michael R. James
Researcher at Los Alamos National Laboratory
Publications - 68
Citations - 2338
Michael R. James is an academic researcher from Los Alamos National Laboratory. The author has contributed to research in topics: Monte Carlo method & Irradiation. The author has an hindex of 19, co-authored 68 publications receiving 1989 citations.
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Journal ArticleDOI
Initial MCNP6 Release Overview
Tim Goorley,Michael R. James,Thomas E. Booth,Forrest B. Brown,Jeffrey S. Bull,L. J. Cox,Joe W. Durkee,Jay S. Elson,Michael L Fensin,R. A. Forster,John S. Hendricks,H. G. Hughes,Russell C. Johns,Brian C. Kiedrowski,Roger L. Martz,Stepan G. Mashnik,Gregg W. McKinney,Denise B. Pelowitz,Richard E. Prael,Jeremy Sweezy,Laurie S. Waters,Trevor Wilcox,T. Zukaitis +22 more
TL;DR: High confidence in the MCNP6 code is based on its performance with the verification and validation test suites, comparisons to its predecessor codes, the regression test suite, its code development process, and the underlying high-quality nuclear and atomic databases.
Proceedings ArticleDOI
The MCNPX Monte Carlo Radiation Transport Code
Laurie S. Waters,Gregg W. McKinney,Joe W. Durkee,Michael L Fensin,John S. Hendricks,Michael R. James,Russell C. Johns,Denise B. Pelowitz +7 more
TL;DR: MCNPX as mentioned in this paper is a general-purpose Monte Carlo radiation transport code with three-dimensional geometry and continuous energy transport of 34 particles and light ions, including neutrons, photons and electrons.
ReportDOI
MCNPX 2.7.0 extensions
Journal ArticleDOI
The mechanical properties of 316L/304L stainless steels, Alloy 718 and Mod 9Cr–1Mo after irradiation in a spallation environment
Stuart A. Maloy,Michael R. James,Gordon Willcutt,Walter F. Sommer,Mikhail A. Sokolov,Lance Lewis Snead,Margaret L. Hamilton,Francis A. Garner +7 more
TL;DR: In this article, the effect of irradiation on the tensile and fracture toughness properties of candidate tritium materials, 316L and 304L stainless steel (annealed), modified (Mod) 9Cr-1Mo steel, and Alloy 718 (precipitation hardened), was measured on various materials irradiated at the Los Alamos Neutron Science Center accelerator.
Journal ArticleDOI
Features of MCNP6
Tim Goorley,Michael R. James,Thomas E. Booth,Forrest B. Brown,Jeffrey S. Bull,L. J. Cox,Joe W. Durkee,Jay S. Elson,Michael L Fensin,R. A. Forster,John S. Hendricks,H. G. Hughes,Russell C. Johns,Brian C. Kiedrowski,Roger L. Martz,Stepan G. Mashnik,Gregg W. McKinney,Denise B. Pelowitz,Richard E. Prael,Jeremy Sweezy,Laurie S. Waters,Trevor Wilcox,T. Zukaitis +22 more
TL;DR: High confidence in the MCNP6 code is based on its performance with the verification and validation test suites, comparisons to its predecessor codes, the authors' automated nightly software debugger tests, the underlying high quality nuclear and atomic databases, and significant testing by many beta testers.