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Title: Status of Monte Carlo at Los Alamos

At Los Alamos the early work of Fermi, von Neumann, and Ulam has been developed and supplemented by many followers, notably Cashwell and Everett, and the main product today is the continuous-energy, general-purpose, generalized-geometry, time-dependent, coupled neutron-photon transport code called MCNP. The Los Alamos Monte Carlo research and development effort is concentrated in Group X-6. MCNP treats an arbitrary three-dimensional configuration of arbitrary materials in geometric cells bounded by first- and second-degree surfaces and some fourth-degree surfaces (elliptical tori). Monte Carlo has evolved into perhaps the main method for radiation transport calculations at Los Alamos. MCNP is used in every technical division at the Laboratory by over 130 users about 600 times a month accounting for nearly 200 hours of CDC-7600 time.
Authors:
;
Publication Date:
OSTI Identifier:
5445647
Report Number(s):
LA-UR-80-1158; CONF-800471-3
TRN: 80-010498
DOE Contract Number:
W-7405-ENG-36
Resource Type:
Conference
Resource Relation:
Conference: Seminar on theory and applications of Monte Carlo methods, Oak Ridge, TN, USA, Apr 1980
Research Org:
Los Alamos Scientific Lab., NM (USA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; HIGH ENERGY PHYSICS; MONTE CARLO METHOD; LASL; NUCLEAR PHYSICS; REACTOR KINETICS; COMPUTER CALCULATIONS; COMPUTER CODES; RESEARCH PROGRAMS; KINETICS; NATIONAL ORGANIZATIONS; PHYSICS; US AEC; US DOE; US ERDA; US ORGANIZATIONS 220100* -- Nuclear Reactor Technology-- Theory & Calculation; 990200 -- Mathematics & Computers