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.).
Suzuki, Tomoo;
Hasegawa, Akira;
Tanaka, Shun-ichi;
Nakashima, Hiroshi
[1]
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
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}
}
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}
}