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JAEA Reports

Evaluation of radioactive inventory in JRR-1

Akutsu, Atsushi; Kishimoto, Katsumi; Sukegawa, Takenori; Shimada, Taro

JAERI-Tech 2003-090, 75 Pages, 2004/01

JAERI-Tech-2003-090.pdf:6.83MB

The Japan Research Reactor No.1 (JRR-1) that was constructed first in Japan was permanently shut down after operation from 1957 to 1968. At present, the reactor part is in safe store conditions. The JRR-1 facility is being used as an exhibition room for the time being, and will be dismantled in the future. In consideration of future dismantling of the facility, the radioactive inventory in reactor part was calculated using computer codes that are Two-Dimensional Discrete Ordinates Transport Code (DORT) and Oak Ridge Isotope Generation and Depletion Code (ORIGEN-MD). The average concentration of radioactivity is estimated to be 6.40$$times$$$$10^{5}$$ Bq/g in the core tank as of April, 2002. It is also expected that the low level waste (LLW) weights approximately 400kg and very low level waste (VLLW) weights approximately 14,000kg, and the waste which doesn't need to deal as a radioactive material weights approximately 250,000kg.

JAEA Reports

Study on residual radioactive inventory estimation in reactor decommissioning program (Contract research)

Sukegawa, Takenori; Hatakeyama, Mutsuo; Yanagihara, Satoshi

JAERI-Tech 2001-058, 81 Pages, 2001/09

JAERI-Tech-2001-058.pdf:5.98MB

In general, neutron transport and activation calculation codes are used for residual radioactive inventory estimation; however, it is essential to verify calculations by measurement results because of geometrical complexity of the reactor and so on. The comparison between measured and calculated radioactivity in the JPDR core components showed a relatively good agreement (factor of 2), and it was cleared that water content and weight ratio of steel bars to concrete materials significantly influenced the neutron flux distribution in the biological shield (factor of 2-10 error). The measured radioactivity inside of the reactor pressure vessel wall and at the inner part of the biological shield was compared in detail with the calculations to verify the methodology applied to calculations of radioisotope production. Then it was found that the radioactive inventory could be estimated accurately with combination of calculations and measurement of radioactivity in samples and dose rate distribution for planning of dismantling activities.

Journal Articles

Development of computer systems for planning and management of reactor decommissioning

Yanagihara, Satoshi; Sukegawa, Takenori; Shiraishi, Kunio

Journal of Nuclear Science and Technology, 38(3), p.193 - 202, 2001/03

no abstracts in English

Journal Articles

Evaluation of methodology on radioactive inventory estimation in the Japan power demonstration reactor decommissioning program

Sukegawa, Takenori; Hatakeyama, Mutsuo; Yanagihara, Satoshi

Journal of Nuclear Science and Technology, 37(Suppl.1), p.367 - 371, 2000/03

no abstracts in English

Journal Articles

Estimation of collective external dose during dismantling of JPDR (BWR,90 MWt)

*; Yanagihara, Satoshi; Sukegawa, Takenori; Tanaka, Mitsugu

Nihon Genshiryoku Gakkai-Shi, 33(6), p.574 - 584, 1991/06

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Estimating the costs for Japans JPDR project

Yanagihara, Satoshi; Tanaka, Mitsugu

Energy J., Vol. 12 (Special Issue), p.135 - 148, 1991/00

no abstracts in English

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