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Development of BERMUDA: a radiation transport code system, 1. Neutron transport codes

Technical Report:

Abstract

A radiation transport code system BERMUDA has been developed for one-, two- and three-dimensional geometries. The time-independent transport equation is numerically solved using a direct integration method in a multigroup model, to obtain spatial, angular and energy distributions of neutron, gamma rays or adjoint neutron flux. As to group constants, a library with an any structure of energy groups is capable to be produced from a data base JSSTDL, or by a processing code PROF-GROUCH-G/B, selecting objective nuclear data through a retrieval system EDFSRS. Validity of the present code system has been tested by analyzing the shielding benchmark experiments. The test has shown that accurate results are obtainable with this system especially in deep penetration calculation. Described are the devised calculation method and the results of validity tests. Input data specification, job control languages and output data are also described as a user`s manual for the following four neutron transport codes: BERMUDA-1DN : sphere, slab(S{sub 20}), BERMUDA-2DN : cylinder (S{sub 8}), BERMUDA-2DN-S16 : cylinder (S{sub 16}), and BERMUDA-3DN : rectangular parallelpiped (S{sub 8}). (J.P.N.).
Authors:
Suzuki, Tomoo; Hasegawa, Akira; Tanaka, Shun-ichi; Nakashima, Hiroshi [1] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
May 01, 1992
Product Type:
Technical Report
Report Number:
JAERI-1327
Reference Number:
SCA: 990200; 663610; PA: JPN-92:011195; SN: 93000918600
Resource Relation:
Other Information: PBD: May 1992
Subject:
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; NEUTRON TRANSPORT; COMPUTER PROGRAM DOCUMENTATION; B CODES; SHIELDING; MULTIGROUP THEORY; NEUTRON FLUX; DIFFERENTIAL CROSS SECTIONS; GROUP CONSTANTS; GAMMA RADIATION; ANGULAR DISTRIBUTION; NEUTRON SPECTRA; MANUALS; 990200; 663610; MATHEMATICS AND COMPUTERS; NEUTRON PHYSICS
OSTI ID:
10111232
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE93753274; TRN: JP9211195
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
119 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Suzuki, Tomoo, Hasegawa, Akira, Tanaka, Shun-ichi, and Nakashima, Hiroshi. Development of BERMUDA: a radiation transport code system, 1. Neutron transport codes. Japan: N. p., 1992. Web.
Suzuki, Tomoo, Hasegawa, Akira, Tanaka, Shun-ichi, & Nakashima, Hiroshi. Development of BERMUDA: a radiation transport code system, 1. Neutron transport codes. Japan.
Suzuki, Tomoo, Hasegawa, Akira, Tanaka, Shun-ichi, and Nakashima, Hiroshi. 1992. "Development of BERMUDA: a radiation transport code system, 1. Neutron transport codes." Japan.
@misc{etde_10111232,
title = {Development of BERMUDA: a radiation transport code system, 1. Neutron transport codes}
author = {Suzuki, Tomoo, Hasegawa, Akira, Tanaka, Shun-ichi, and Nakashima, Hiroshi}
abstractNote = {A radiation transport code system BERMUDA has been developed for one-, two- and three-dimensional geometries. The time-independent transport equation is numerically solved using a direct integration method in a multigroup model, to obtain spatial, angular and energy distributions of neutron, gamma rays or adjoint neutron flux. As to group constants, a library with an any structure of energy groups is capable to be produced from a data base JSSTDL, or by a processing code PROF-GROUCH-G/B, selecting objective nuclear data through a retrieval system EDFSRS. Validity of the present code system has been tested by analyzing the shielding benchmark experiments. The test has shown that accurate results are obtainable with this system especially in deep penetration calculation. Described are the devised calculation method and the results of validity tests. Input data specification, job control languages and output data are also described as a user`s manual for the following four neutron transport codes: BERMUDA-1DN : sphere, slab(S{sub 20}), BERMUDA-2DN : cylinder (S{sub 8}), BERMUDA-2DN-S16 : cylinder (S{sub 16}), and BERMUDA-3DN : rectangular parallelpiped (S{sub 8}). (J.P.N.).}
place = {Japan}
year = {1992}
month = {May}
}