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Monte Carlo methods for particle transport

Conference · · Transactions of the American Nuclear Society; (USA)
OSTI ID:6434959
 [1];
  1. Univ. of Michigan, Ann Arbor (USA)

Monte Carlo codes for simulating particle transport were among the first applications of computers in the 1940s. Since then, advances in computer hardware, software, Monte Carlo methodology, and cross-section data availability have led to the development of a large number of general-purpose Monte Carlo production codes. Today these codes are used extensively to simulate particle transport in applications such as reactor core analysis, radiation shielding, particle detector design and analysis, oil-well logging, high-energy particle physics simulation, etc. A partial list of general-purpose production codes includes MCNP, MORSE, KENO, TART, MONK6, TRIPOLI, SAM-CE, RCP, PACER, 05R, RACER, GEANT, and McBEND. There have been a number of recent review papers on Monte Carlo methods, including one that focused on variance reduction techniques and one that summarized the status of vectorized Monte Carlo. Therefore, this paper addresses several broader topics: What capabilities are common to typical production-level Monte Carlo codes Why are there so many production codes What are current areas of interest for Monte Carlo methods development What is the impact of advanced computer architectures on Monte Carlo methods

OSTI ID:
6434959
Report Number(s):
CONF-891103--
Journal Information:
Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 60; ISSN TANSA; ISSN 0003-018X
Country of Publication:
United States
Language:
English