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Monte Carlo methods for radiation transport analysis on vector computers

dc.contributor.authorBrown, Forrest B.en_US
dc.contributor.authorMartin, William R.en_US
dc.date.accessioned2006-04-07T18:34:25Z
dc.date.available2006-04-07T18:34:25Z
dc.date.issued1984en_US
dc.identifier.citationBrown, Forrest B., Martin, William R. (1984)."Monte Carlo methods for radiation transport analysis on vector computers." Progress in Nuclear Energy 14(3): 269-299. <http://hdl.handle.net/2027.42/24996>en_US
dc.identifier.urihttp://www.sciencedirect.com/science/article/B6V3X-498159Y-CN/2/5f6b17875e0fced0eb5dee5a47132639en_US
dc.identifier.urihttps://hdl.handle.net/2027.42/24996
dc.description.abstractThe development of advanced computers with special capabilities for vectorized or parallel calculations demands the development of new calculational methods. The very nature of the Monte Carlo process precludes direct conversion of old (scalar) codes to the new machines. Instead, major changes in global algorithms and careful selection of compatible physics treatments are required. Recent results for Monte Carlo in multigroup shielding applications and in continuous-energy reactor lattice analysis have demonstrated that Monte Carlo methods can be successfully vectorized. The significant effort required for stylized coding and major algorithmic changes is worthwhile, and significant gains in computational efficiency are realized. Speedups of at least twenty to forty times faster than CDC-7600 scalar calculations have been achieved on the CYBER-205 without sacrificing the accuracy of standard Monte Carlo methods. Speedups of this magnitude provide reductions in statistical uncertainties for a given amount of computing time, permit more detailed and realistic problems to be analyzed, and make the Monte Carlo method more accessible to nuclear analysts. Following overviews of the Monte Carlo method for particle transport analysis and of vector computer hardware and software characteristics, both general and specific aspects of the vectorization of Monte Carlo are discussed. Finally, numerical results obtained from vectorized Monte Carlo codes run on the CYBER-205 are presented.en_US
dc.format.extent2653176 bytes
dc.format.extent3118 bytes
dc.format.mimetypeapplication/pdf
dc.format.mimetypetext/plain
dc.language.isoen_US
dc.publisherElsevieren_US
dc.titleMonte Carlo methods for radiation transport analysis on vector computersen_US
dc.typeArticleen_US
dc.rights.robotsIndexNoFollowen_US
dc.subject.hlbsecondlevelPhysicsen_US
dc.subject.hlbsecondlevelNuclear Engineering and Radiological Sciencesen_US
dc.subject.hlbtoplevelScienceen_US
dc.subject.hlbtoplevelEngineeringen_US
dc.description.peerreviewedPeer Revieweden_US
dc.contributor.affiliationumDepartment of Nuclear Engineering, University of Michigan, Ann Arbor, Michigan, U.S.A.en_US
dc.contributor.affiliationumDepartment of Nuclear Engineering, University of Michigan, Ann Arbor, Michigan, U.S.A.en_US
dc.description.bitstreamurlhttp://deepblue.lib.umich.edu/bitstream/2027.42/24996/1/0000423.pdfen_US
dc.identifier.doihttp://dx.doi.org/10.1016/0149-1970(84)90024-6en_US
dc.identifier.sourceProgress in Nuclear Energyen_US
dc.owningcollnameInterdisciplinary and Peer-Reviewed


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