Evaluation of neutron flux and gamma heating for irradiation tests of JMTR

Nagao, Yoshiharu ; Itabashi, Yukio; Komori, Yoshihiro ; Niimi, Motoji; Fujiki, Kazuo

An improved analysis procedure has been introduced to evaluate irradiation field at each specimen in the irradiation capsule by using the MCNP code, which is able to model the complicated structure of the capsule directly. As the verification results, it was confirmed that the calculated fast and thermal neutron flux/fluence were agreed with measured ones within 10% and 30%, respectively, for the irradiation tests in the JMTR. Concerning gamma dose/spectrum, it was confirmed that the calculated temperature was evaluated within -3+14% using gamma heating obtained by MCNP calculations. The evaluations of neutron flux/fluence and specimens temperature with high accuracy are therefore possible in the irradiation test of the JMTR.

Language	:	English
Journal	:	KAERI/GP-195/2002
Volume	:
Number	:
Pages	:	p.49 - 55
Publication Year/Month	:	2002/00
Meeting title	:	2002 KAERI-JAERI Joint Seminar on Irradiation Technology
Held date	:	2002/10
Location (city)	:	Daejeon
Location (country)	:	Korea
Patent information	:
PDF	:
Paper URL	:
DOI for research data	:
Keywords	:	JMTR; MCNP; Neutron Flux; Gamma Heating; Monte Carlo; Specimen Temperature
Research Facility	:	JMTR(材料試験炉)
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:

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Registration No. : B20021436
JAEA Abstracts No. : 310294
Paper Submission No. : 19924

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