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Nagaya, Yasunobu; Okumura, Keisuke; Sakurai, Takeshi; Mori, Takamasa
JAEA-Data/Code 2016-018, 421 Pages, 2017/03
JAEA-Data-Code-2016-018.pdf:3.89MB
JAEA-Data-Code-2016-018-appendix(CD-ROM).zip:4.02MBJAEA-Data-Code-2016-018-hyperlink.zip:1.94MB
In order to realize fast and accurate Monte Carlo simulation of neutron and photon transport problems, two Monte Carlo codes MVP (continuous-energy method) and GMVP (multigroup method) have been developed at Japan Atomic Energy Agency. The codes have adopted a vectorized algorithm and have been developed for vector-type supercomputers. They also support parallel processing with a standard parallelization library MPI and thus a speed-up of Monte Carlo calculations can be achieved on general computing platforms. The first and second versions of the codes were released in 1994 and 2005, respectively. They have been extensively improved and new capabilities have been implemented. The major improvements and new capabilities are as follows: (1) perturbation calculation for effective multiplication factor, (2) exact resonant elastic scattering model, (3) calculation of reactor kinetics parameters, (4) photo-nuclear model, (5) simulation of delayed neutrons, (6) generation of group constants, etc. This report describes the physical model, geometry description method used in the codes, new capabilities and input instructions.
Nagaya, Yasunobu; Okumura, Keisuke; Mori, Takamasa; Nakagawa, Masayuki
JAERI 1348, 388 Pages, 2005/06
To realize fast and accurate Monte Carlo simulation of neutron and photon transport problems, two vectorized Monte Carlo codes MVP and GMVP have been developed at JAERI. MVP is based on the continuous energy model and GMVP is on the multigroup model. Compared with conventional scalar codes, these codes achieve higher computation speed by a factor of 10 or more on vector supercomputers. Both codes have sufficient functions for production use by adopting accurate physics model, geometry description capability and variance reduction techniques. The first version of the codes was released in 1994. They have been extensively improved and new functions have been implemented. The major improvements and new functions are (1) capability to treat the scattering model expressed with File 6 of the ENDF-6 format, (2) time-dependent tallies, (3) reaction rate calculation with the pointwise response function, (4) flexible source specification, etc. This report describes the physical model, geometry description method used in the codes, new functions and how to use them.
M.Rahman*; Takano, Hideki
JAERI-Research 96-056, 51 Pages, 1996/11
JAERI-Research-96-056.pdf:1.76MB
no abstracts in English
Mori, Takamasa; Nakakawa, Masayuki
JAERI-Data/Code 94-007, 152 Pages, 1994/08
JAERI-Data-Code-94-007.pdf:3.92MB
no abstracts in English
Komuro, Yuichi; Okuno, Hiroshi; Naito, Yoshitaka; *; Nagai, Masakatsu*; *; *; *
JAERI-M 93-190, 94 Pages, 1993/10
no abstracts in English
Nakakawa, Masayuki; Mori, Takamasa
Journal of Nuclear Science and Technology, 30(7), p.692 - 701, 1993/07
Times Cited Count：33 Percentile：92.41(Nuclear Science & Technology)no abstracts in English
Mori, Takamasa; Nakakawa, Masayuki; *
Journal of Nuclear Science and Technology, 29(12), p.1224 - 1227, 1992/12
no abstracts in English
Komuro, Yuichi; Okuno, Hiroshi; Naito, Yoshitaka; *; *; *
JAERI-M 90-126, 125 Pages, 1990/08
no abstracts in English
Katakura, Junichi; Okuno, Hiroshi; Naito, Yoshitaka
Proc.Int.Seminar on Nuclear Criticality Safety, p.138 - 144, 1987/00
no abstracts in English
;
JAERI-M 8818, 21 Pages, 1980/04
no abstracts in English
;
Journal of Nuclear Science and Technology, 14(8), p.603 - 609, 1977/08
Times Cited Count：0no abstracts in English
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JAERI-M 5991, 148 Pages, 1975/02
no abstracts in English
*; Katsuragi, Satoru
Nuclear Science and Engineering, 33, p.297 - 302, 1968/00
Times Cited Count：22no abstracts in English
