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Nagaya, Yasunobu; Okumura, Keisuke; Sakurai, Takeshi; Mori, Takamasa
JAEA-Data/Code 2016-018, 421 Pages, 2017/03
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.
Shinohara, Masanori; Ishitsuka, Etsuo; Shimazaki, Yosuke; Sawahata, Hiroaki
JAEA-Technology 2016-033, 65 Pages, 2017/01
To reduce the neutron exposure dose for workers during the replacement works of the startup neutron sources of the High Temperature Engineering Test Reactor, calculations of the exposure dose in case of temporary neutron shielding at the bottom of fuels handling machine were carried out by the PHITS code. As a result, it is clear that the dose equivalent rate due to neutron radiation can be reduced to about an order of magnitude by setting a temporary neutron shielding at the bottom of shielding cask for the fuel handling machine. In the actual replacement works, by setting temporary neutron shielding, it was achieved that the cumulative equivalent dose of the workers was reduced to 0.3 man mSv which is less than half of cumulative equivalent dose for the previous replacement works; 0.7 man mSv.
Iwamoto, Yosuke; Taniguchi, Shingo*; Nakao, Noriaki*; Itoga, Toshio*; Nakamura, Takashi*; Nakane, Yoshihiro; Nakashima, Hiroshi; Satoh, Daiki; Yashima, Hiroshi*; Yamakawa, Hiroshi*; et al.
Nuclear Instruments and Methods in Physics Research A, 562(2), p.789 - 792, 2006/06
Times Cited Count:6 Percentile:43.77(Instruments & Instrumentation)Neutron energy spectra produced from thick targets play an important role in validation of calculation codes that are employed in the design of spallation neutron sources and the shielding design of accelerator facilities. However, appropriate experimental data were scarce in the forward direction for the incident energy higher than 100 MeV. In this study, neutron spectra at 0 degree from thick targets bombarded with 350 MeV protons were measured by the time-of-flight technique using an NE213. The targets used were graphite, Al, Fe and Pb and their thicknesses were chosen to be a little thicker than the stopping lengths. The experiment was carried out at the TOF course of the RCNP (Research Center of Nuclear Physics) ring cyclotron, Osaka University. The flight path length between center of the target and of an NE213 were 11.4 m for the measurement of low energy neutrons and 95 m for high energy neutrons. The experimental data are compared with the calculated results by using the Monte Carlo transport codes, such as MCNPX and PHITS codes.
Yoshizawa, Michio; Endo, Akira
JAERI-Conf 2003-002, 166 Pages, 2003/03
The present report is Proceedings of the Third Workshop on Dosimetry for External Radiations, held at the Tokai Research Establishment, Japan Atomic Energy Research Institute (JAERI), in November 28-29, 2002. The proceedings comprises 16 papers and a summary of general discussion. The Third Workshop, subtitled "On an opportunity of the completion of the facility of calibration standards for neutron at JAERI", focused on neutron dosimetry and included presentations on the status of international neutron standards, the development of calibration techniques of neutron dosimeters using accelerator neutron sources, and dosimetry for high-energy neutrons. The workshop identified the directions for the future research and development in this field.
Takada, Hiroshi; Meigo, Shinichiro; Niita, Koji*
Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications, p.949 - 954, 2001/00
no abstracts in English
Okumura, Keisuke; *;
JAERI-Data/Code 96-015, 445 Pages, 1996/03
no abstracts in English
; Sasa, Toshinobu; Takada, Hiroshi; Takizuka, Takakazu
Proc. of 2nd Int. Conf. on Accelerator-Driven Transmutation Technologies and Applications, 1, p.668 - 674, 1996/00
no abstracts in English
Mori, Takamasa; Kosako, Kazuaki*
Purazuma, Kaku Yugo Gakkai-Shi, 71(12), p.1212 - 1219, 1995/12
no abstracts in English
; ; Suzuki, Tomoo
JAERI-Data/Code 95-006, 98 Pages, 1995/06
no abstracts in English
Suzuki, Tomoo*; ; Tanaka, Shunichi;
JAERI-Data/Code 94-002, 22 Pages, 1994/07
no abstracts in English
Suzuki, Tomoo; ; Tanaka, Shunichi;
JAERI 1327, 110 Pages, 1992/05
no abstracts in English
Mori, Takamasa; Nakakawa, Masayuki; *
Journal of Nuclear Science and Technology, 29(4), p.325 - 336, 1992/04
no abstracts in English
Yamano, Naoki*; Minami, Kazuyoshi*; ; Naito, Yoshitaka
JAERI 1316, 307 Pages, 1989/03
no abstracts in English
Mori, Takamasa; *; Nakakawa, Masayuki
JAERI-M 87-123, 55 Pages, 1987/08
no abstracts in English
; ;
JAERI-M 87-010, 28 Pages, 1987/02
no abstracts in English
*
JAERI-M 85-017, 298 Pages, 1985/03
no abstracts in English
Nakagawa, Masayuki;
JAERI-M 84-126, 74 Pages, 1984/07
no abstracts in English
JAERI-M 84-038, 116 Pages, 1984/03
no abstracts in English
; *;
JAERI-M 83-144, 40 Pages, 1983/09
no abstracts in English
;
Journal of Fusion Energy, 3(5-6), p.421 - 424, 1983/00
no abstracts in English