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Journal Articles

Summary report on the joint session entitled by "Decommissioning of reactor and accelerator facilities and present status of activation nuclear data libraries"

Nakamura, Shoji

Kaku Deta Nyusu (Internet), (115), p.18 - 23, 2016/10

This is a summary report on the planning joint session entitled by "Decommissioning of reactor and accelerator facilities and present status of activation nuclear data libraries".

JAEA Reports

Evaluation on activation activity of reactor in JRR-2 applied 3 dimensional model to neutron flux calculation

Kishimoto, Katsumi; Arigane, Kenji*

JAERI-Tech 2005-016, 83 Pages, 2005/03

JAERI-Tech-2005-016.pdf:10.52MB

Revaluation to activation activity of reactor evaluated at the notification of dismantling submitted in 1997 was carried out in JRR-2 where decommissioning was advanced now. In the revaluation, estimation accuracy on neutron streaming at various horizontal experimental tubes was improved by applying 3 dimensional model to neutron transport calculation that had been carried out by 2 dimensional model, and calculating with TORT. As the result, excessive overestimations on horizontal experimental tubes and biological shield that had greatly contributed to total activation activity in evaluation at the notification of dismantling was revised, sum of their activation activities in the revaluation decreased to 1/18(case after 1 year from the permanent shutdown of reactor) of evaluation at the notification of dismantling, and the structural materials that had large activation activity were changed. By the above, it was shown that introducing 3 dimensional model was effective in evaluation on activation activity of the research reactor that had a lot of various experimental tubes.

Journal Articles

Recent activities on clearance by IAEA and Japanese organizations

Okoshi, Minoru

Dekomisshoningu Giho, (31), p.32 - 44, 2005/03

The International Atomic Energy Agency (IAEA) published a Safety Guide (RS-G-1.7) on the application of the concepts of exclusion, exemption and clearance in 2004. In this Safety Guide, the IAEA proposes the activity concentrations can be applied to clearance. The Nuclear Safety Commission reevaluated their clearance levels to reflect the new technological information given in the IAEA Safety Guide and other reports. The Regulatory Authorities have been investigating and discussing regulatory rules on clearance including the verification system of clearance levels. And the Atomic Society of Japan has deliberated the technological standards for the verification of clearance levels performed by nuclear operators. In this paper the activities and outcomes by those organizations are outlined, and the issues to be solved on clearance are listed and the basic ideas for solution are discussed.

JAEA Reports

JRR-2 decommissioning activity, 1

Nakano, Masahiro; Arigane, Kenji; Okawa, Hiroshi; Suzuki, Takeshi; Kishimoto, Katsumi; Terunuma, Akihiro; Yano, Masaaki; Sakuraba, Naotoshi; Oba, Nagamitsu

JAERI-Tech 2003-072, 92 Pages, 2003/08

JAERI-Tech-2003-072.pdf:6.99MB

The decommissioning plan of the Japan Research reactor No2(JRR-2), decommissioning activities until the first half of phase-3, radioactive wastes and exposure dose of workers are described in this report. Since the first criticality in October 1960, JRR-2 had been operated about 36 years for various experiments. However, JRR-2 was permanent shutdown in December 1996 based on JAERI's long term plan, and the decommissioning of the JRR-2 was started in August 1997. Decommissioning of the JRR-2 was planed for 11 years from 1997 to 2007 and the program was divided into 4 phases. The decommissioning activities of the phase-1, phase-2 and the first half of phase-3 had already completed as planned in March 1998, February 2000, March 2002, respectively. The decommissioning activities of the later half of Phase-3 (dismantling of the reactor cooling systems) are carrying out at present time with planed 2002 and 2003 fiscal years.

JAEA Reports

Carbon-14 in neutron-irradiated graphite for graphite-moderated reactors (Joint research)

Fujii, Kimio; Matsuo, Hideto*

JAERI-Review 2002-034, 44 Pages, 2002/12

JAERI-Review-2002-034.pdf:3.34MB

Graphite material is used as a moderator and reflector of graphite-moderated gas-cooled reactors such as the Tokai Nuclear Power Station of Japan Atomic Power Company. For the decommissioning of those reactors, it is very important to obtain the density of carbon-14 in the graphite of which half-time is very long, and the development of the reduction technique for density of carbon-14 is one of the main technical issues as well. The reactor ceased the commercial operation on March 1998, and is in the process of the decommissioning. Technical developement on nuclear graphite disposal is one of the main issues, and it is pointed out that carbon-14 density is an impotant factor for the treatment on the disposal of the nuclear graphite. In order to resolve the problem, literatures survey was carried out for describing the status of technical development on resolving the problem. This report describes the outline of the literatures surveyed and the list of the related literatures is attached as well.

JAEA Reports

Annual report of Department of Research Reactor 2001; April 1, 2001 - March 31, 2002

Department of Research Reactor

JAERI-Review 2002-033, 215 Pages, 2002/12

JAERI-Review-2002-033.pdf:16.19MB

no abstracts in English

JAEA Reports

Annual report of Department of Research Reactor 2000; April 1, 2000 - March 31, 2001

Department of Research Reactor

JAERI-Review 2001-048, 216 Pages, 2002/02

JAERI-Review-2001-048.pdf:17.83MB

no abstracts in English

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.

JAEA Reports

Annual report of Department of Research Reactor 1999; April 1, 1999 - March 31, 2000

Department of Research Reactor

JAERI-Review 2000-036, 263 Pages, 2001/03

JAERI-Review-2000-036.pdf:19.89MB

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

JAEA Reports

Annual report of Department of Research Reactor, 1998; April 1, 1998 $$sim$$ March 31, 1999

Department of Research Reactor

JAERI-Review 99-032, p.232 - 0, 2000/02

JAERI-Review-99-032.pdf:11.62MB

no abstracts in English

Journal Articles

Design concept of disposal systems for highly activated waste

Okoshi, Minoru; Abe, Masayoshi; Yoshimori, Michiro; Sakai, Akihiro

Proc. of Waste Management'98 (CD-ROM), 5 Pages, 1998/00

no abstracts in English

Journal Articles

Near surface disposal of very low level waste generated from reactor decommissioning and related safety requirements

Okoshi, Minoru; Yoshimori, Michiro; Abe, Masayoshi

Planning and Operation of Low Level Waste Disposal Facilities IAEA-SM-341/70, 0(0), p.416 - 425, 1997/00

no abstracts in English

Journal Articles

Contamination control, clearing and radiation monitoring in nuclear research facilities

Ikezawa, Yoshio

Saikin No Kenkyu Shisetsu, 0, p.304 - 311, 1995/00

no abstracts in English

Journal Articles

Waste characterization in decommissioning the Japan Power Demonstration Reactor by computer code systems

Sukegawa, Takenori; ; ; Yanagihara, Satoshi

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 4, 0, p.1779 - 1784, 1995/00

no abstracts in English

Journal Articles

Progress of research and development in Japan Atomic Energy Research Institute

Saito, Shinzo

Denki Hyoron, 0(2), p.57 - 63, 1994/02

no abstracts in English

Journal Articles

Status of research reactor decommissioning in Japan

Onishi, Nobuaki; Shirai, Eiji

Proc. of the 9th Pacific Basin Nuclear Conf., Vol. 2, p.1071 - 1076, 1994/00

no abstracts in English

45 (Records 1-20 displayed on this page)