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MVP/GMVP: general purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods

Technical Report:

Abstract

In order to realize fast and accurate Monte Carlo simulation of neutron and photon transport problems, new algorithms have been studied, and two fully vectorized Monte Carlo codes MVP and GMVP have been developed for FACOM VP series vector supercomputers. The former and latter codes use the continuous energy model and the multi-group model, respectively. Compared with conventional scalar codes, these codes achieve higher computation speed by a factor of 10 or more on FACOM VP-2600. Both codes have functions for production use including accurate physics model, geometry description capability and variance reduction technique. In addition to the execution on the vector supercomputers, these codes can be used on vector-parallel supercomputers with parallel calculation capability and on workstations with an OS of UNIX. For the continuous energy method, many nuclear data libraries have been prepared based on mainly JENDL 3. This report describes the physics model, geometry description method used in the codes and how to use them. (author).
Authors:
Mori, Takamasa; Nakagawa, Masayuki [1] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Aug 01, 1994
Product Type:
Technical Report
Report Number:
JAERI-Data/Code-94-007
Reference Number:
SCA: 990200; 663610; 663620; PA: JPN-94:011230; EDB-95:011690; SN: 95001296264
Resource Relation:
Other Information: PBD: Aug 1994
Subject:
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; ALGORITHMS; NEUTRON TRANSPORT; PHOTON TRANSPORT; MONTE CARLO METHOD; SIMULATION; M CODES; G CODES; VECTOR PROCESSING; ACCURACY; MANUALS; COMPUTER PROGRAM DOCUMENTATION; 990200; 663610; 663620; MATHEMATICS AND COMPUTERS; NEUTRON PHYSICS; PHYSICS OF RADIATIONS OTHER THAN NEUTRONS
OSTI ID:
10102300
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE95722072; TRN: JP9411230
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
160 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Mori, Takamasa, and Nakagawa, Masayuki. MVP/GMVP: general purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods. Japan: N. p., 1994. Web.
Mori, Takamasa, & Nakagawa, Masayuki. MVP/GMVP: general purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods. Japan.
Mori, Takamasa, and Nakagawa, Masayuki. 1994. "MVP/GMVP: general purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods." Japan.
@misc{etde_10102300,
title = {MVP/GMVP: general purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods}
author = {Mori, Takamasa, and Nakagawa, Masayuki}
abstractNote = {In order to realize fast and accurate Monte Carlo simulation of neutron and photon transport problems, new algorithms have been studied, and two fully vectorized Monte Carlo codes MVP and GMVP have been developed for FACOM VP series vector supercomputers. The former and latter codes use the continuous energy model and the multi-group model, respectively. Compared with conventional scalar codes, these codes achieve higher computation speed by a factor of 10 or more on FACOM VP-2600. Both codes have functions for production use including accurate physics model, geometry description capability and variance reduction technique. In addition to the execution on the vector supercomputers, these codes can be used on vector-parallel supercomputers with parallel calculation capability and on workstations with an OS of UNIX. For the continuous energy method, many nuclear data libraries have been prepared based on mainly JENDL 3. This report describes the physics model, geometry description method used in the codes and how to use them. (author).}
place = {Japan}
year = {1994}
month = {Aug}
}