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Imaizumi, Tomomi; Miyauchi, Masaru; Ito, Masayasu; Watahiki, Shunsuke; Nagata, Hiroshi; Hanakawa, Hiroki; Naka, Michihiro; Kawamata, Kazuo; Yamaura, Takayuki; Ide, Hiroshi; et al.
JAEA-Technology 2011-031, 123 Pages, 2012/01
JAEA-Technology-2011-031.pdf:16.08MB
The number of research reactors in the world is decreasing because of their aging. However, the planning to introduce the nuclear power plants is increasing in Asian countries. In these Asian countries, the key issue is the human resource development for operation and management of nuclear power plants after constructed them, and also the necessity of research reactor, which is used for lifetime extension of LWRs, progress of the science and technology, expansion of industry use, human resources training and so on, is increasing. From above backgrounds, the Neutron Irradiation and Testing Reactor Center began to discuss basic concept of a multipurpose low-power research reactor for education and training, etc. This design study is expected to contribute not only to design tool improvement and human resources development in the Neutron Irradiation and Testing Reactor Center but also to maintain and upgrade the technology on research reactors in nuclear power-related companies. This report treats the activities of the working group from July 2010 to June 2011 on the multipurpose low-power research reactor in the Neutron Irradiation and Testing Reactor Center and nuclear power-related companies.
Tagami, Susumu; Shimizu, Osamu; Sano, Naruto; Imaizumi, Akiko; Tobita, Hiroshi; Nagasaki, Yosuke; Kurobane, Shiro
JAEA-Review 2010-079, 90 Pages, 2011/03
JAEA-Review-2010-079.pdf:3.02MB
The Back-end Cycle Key Elements Research Facility (BECKY) was installed in the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) in 1994 for the safety and basic studies of the nuclear fuel cycle and radioactive waste. BECKY consists of three alpha/
concrete cells, three alpha/ steel cells, thirty glove boxes and twenty hoods. Operation, maintenance and management are in execution based on the operational safety programs. And we also execute application about amendment of the permission and approval for the purpose of support R&D. This report describes the operation, maintenance and management from April 1, 2005 to March 31, 2010 for the purpose of keeping the performance of BECKY.
Shinohara, Kunihiko; ; ; ; ; Kano, Yutaka;
JNC TN8440 2001-004, 62 Pages, 2001/02
JNC-TN8440-2001-004.pdf:4.17MB
Concerming about the action for the criticality accident in JCO Co., Ltd. (JCO) occurred at 10:35 on 30
Sept. 1999, Japan Nuclear Cycle Development Institute(JNC) established "JNC's task force" at 12:35 on the same date in conjuction with Head Office and Tokai Works. And JNC's task force had supported the government of Japan, the local governments and JCO humanly, physically and technically until the jobs of the task force was transferred to "Support Assembly for Countermeasure and Research of JCO Criticality Accident" and routine line on 12 Oct. 1999. This report compiled the results of the environmental monitoring performed by JNC based on the request from the government of Japan and the local governments.
; Shinohara, Kunihiko; ; ; ; Takeyasu, Masanori;
JNC TN8440 2000-007, 141 Pages, 2000/06
JNC-TN8440-2000-007.pdf:3.02MB
Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed since 1975, based on "Safety Regulations for the Tokai Reprocessing Plant, Chapter IV - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitants due to the radioactivity discharged from the plant during April 1999 to March 2000. Appendices present comprehensive information, such as monitoring program, monitoring results, meteorological data and annual discharges from the plant.
; ; ; ; ; ;
JNC TN8440 99-008, 146 Pages, 1999/06
Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed since 1975, based on "Safety Regulations for the Tokai Reprocessing Plant, Chapter IV - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitants due to the radioactivity discharged from the plant during April 1998 to March 1999. Appendices present comprehensive information. such as monitoring program. monitoring results, meteorological data and annual discharges from the plant.
; ; Takeyasu, Masanori; ; ; ;
PNC TN8440 98-022, 140 Pages, 1998/06
Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed since 1975, based on "Safety Regulations for the Tokai Reprocessing Plant, Chapter VII - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitants due to the radioactivity discharged from the plant during April 1997 to March 1998. Appendices present comprehensive information, such as monitoring program, monitoring results, meteorological data and annual discharges from the plant.
; ; Kano, Yutaka; ; ; ;
PNC TN8440 97-022, 147 Pages, 1997/05
Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed since 1975, based on "Safety Regulations for the Tokai Reprocessing Plant, Chapter VII - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitants due to the radioactivity discharged from the plant during April 1996 to March 1997. Dose estimation includes unplanned discharges during fire and explosion at the Bituminization Facility of the TRP on March 11th. Appendices present comprehensive information, such as monitoring program, monitoring results, meteorological data and annual discharges from the plant.
; ; ; ; Kano, Yutaka
PNC TN8420 96-017, 50 Pages, 1996/08
The meteorological observation has been performed since 1955 in PNC Tokai-works. After 1974, this observation came to measure on the top of the meteorological tower (100m above sea level) for the environmental assessment of a radioactive waste with the atmospheric discharge from the reprocessing plant. This report presents an atmospheric phenomenon statistic result and an examination about a characteristic of the atmosphere diffusion based on the data from 1977 to 1995. Characteristics of the result are as follows; (1)It was confirmed that the maximum air concentration point that was calculated based on the discharge amount from reprocessing plant and atmospheric phenomenon statistic of each year appears at near point in the safety assessment of 1977. (2)In some case, a maximum concentration point has appeared at about 800m in the west-southwest direction owing to the deference of appearance frequency of the atmospheric stability, etc. Normally it appears at about 2,000m point in south-west direction. Still, as reference materials, atmospheric phenomenon statistics result and relative concentration were mentioned.
*; *; *; *; *; Hirose, Tadashi*; *
PNC TN941 79-161, 50 Pages, 1979/10
A radionuclide-analysis and a determination of activity of the waste argon and nitrogen gas were carried out during the power ascension test. The sampling of the gas was carried out by means of stainless steel vaccum vessels or vinyl bags and gamma activities were analyzed with a multi channel pulse height analyzer (MCA) and a vibrating reed electrometer (VRE). 
Ar was observed as the major part of gamma activity. In addition to Ar, some long-lived radionuclides were observed in the decay measurement with VRE. Concerning long-lived radionuclides, it was confirmed that some amounts of 
H existed as a part of activity and some amounts of 
C were considered to be in the waste gas by judging several charactiristic informations of the gas. The concentration of radionuclides in the waste gas were also evaluated. No relationship between the concentrations and a reactor power were found. Above results, however, indicated such general tendency that the concentration of this long-lived radionuclides released from the argon and nitrogen waste gas are H and Ar. The values of concentrations of the radionuclides and release rates of the waste gas were well below the control criteria in this test period.