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Core calculations of JMTR

Abstract

In material testing reactors like the JMTR (Japan Material Testing Reactor) of 50 MW in Japan Atomic Energy Research Institute, the neutron flux and neutron energy spectra of irradiated samples show complex distributions. It is necessary to assess the neutron flux and neutron energy spectra of an irradiation field by carrying out the nuclear calculation of the core for every operation cycle. In order to advance core calculation, in the JMTR, the application of MCNP to the assessment of core reactivity and neutron flux and spectra has been investigated. In this study, in order to reduce the time for calculation and variance, the comparison of the results of the calculations by the use of K code and fixed source and the use of Weight Window were investigated. As to the calculation method, the modeling of the total JMTR core, the conditions for calculation and the adopted variance reduction technique are explained. The results of calculation are shown. Significant difference was not observed in the results of neutron flux calculations according to the difference of the modeling of fuel region in the calculations by K code and fixed source. The method of assessing the results of neutron flux calculation is described.  More>>
Authors:
Nagao, Yoshiharu [1] 
  1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Publication Date:
Mar 01, 1998
Product Type:
Technical Report
Report Number:
JAERI-Review-98-010
Reference Number:
SCA: 220600; PA: JPN-98:006313; EDB-98:078194; SN: 98001981584
Resource Relation:
Other Information: PBD: Mar 1998; Related Information: Is Part Of Use experiences of MCNP in nuclear energy study. 2. Review of variance reduction techniques; Sakurai, Kiyoshi; Yamamoto, Toshihiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [eds.]; PB: 313 p.
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; JMTR REACTOR; REACTOR CORES; NEUTRON FLUX; NEUTRON SPECTRA; FAST NEUTRONS; THERMAL NEUTRONS; NEUTRON TRANSPORT; MONTE CARLO METHOD; COMPUTER CALCULATIONS; ACCURACY; M CODES
OSTI ID:
630030
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE98755716; TRN: JP9806313
Availability:
OSTI as DE98755716
Submitting Site:
JPN
Size:
pp. 128-165
Announcement Date:

Citation Formats

Nagao, Yoshiharu. Core calculations of JMTR. Japan: N. p., 1998. Web.
Nagao, Yoshiharu. Core calculations of JMTR. Japan.
Nagao, Yoshiharu. 1998. "Core calculations of JMTR." Japan.
@misc{etde_630030,
title = {Core calculations of JMTR}
author = {Nagao, Yoshiharu}
abstractNote = {In material testing reactors like the JMTR (Japan Material Testing Reactor) of 50 MW in Japan Atomic Energy Research Institute, the neutron flux and neutron energy spectra of irradiated samples show complex distributions. It is necessary to assess the neutron flux and neutron energy spectra of an irradiation field by carrying out the nuclear calculation of the core for every operation cycle. In order to advance core calculation, in the JMTR, the application of MCNP to the assessment of core reactivity and neutron flux and spectra has been investigated. In this study, in order to reduce the time for calculation and variance, the comparison of the results of the calculations by the use of K code and fixed source and the use of Weight Window were investigated. As to the calculation method, the modeling of the total JMTR core, the conditions for calculation and the adopted variance reduction technique are explained. The results of calculation are shown. Significant difference was not observed in the results of neutron flux calculations according to the difference of the modeling of fuel region in the calculations by K code and fixed source. The method of assessing the results of neutron flux calculation is described. (K.I.)}
place = {Japan}
year = {1998}
month = {Mar}
}