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Hasegawa, Ken; Kunitomo, Takahiro; Nakajima, Takahiro*; Asai, Hideaki*; Iyatomi, Yosuke; Matsui, Hiroya
JAEA-Evaluation 2011-001, 150 Pages, 2011/06
JAEA-Evaluation-2011-001.pdf:28.92MB
ACROSS has developed to acquire the detailed information on the tectonically active zone. The technology for example the transmission and receiving technique, the data analysis and the interpretation technique of the ACROSS signal is able to apply not only to seismology but also to other field. We considered the ACROSS technology may apply to the engineering technology of the MIU project, for example monitoring of the change of the geological environment around shafts and also the strength of the shaft concrete itself. It is planned that the examination for three years will be made from fiscal year 2007. The first year is expansion of the network of observation stations, the second year is data acquisition and last year is the analysis of data and evaluation of the ACROSS. In this report, we describe the results of fundamental studies of the ACROSS and the processing results obtained from the ACROSS observation stations which were prepared in fiscal year 2007 and 2008, also describe the current evaluation results of the ACROSS.
FBR Plant Engineering Center; Fast Breeder Reactor Research and Development Center, Tsuruga Head Office
JAEA-Evaluation 2011-002, 96 Pages, 2011/06
JAEA-Evaluation-2011-002.pdf:6.65MB
The results of Core Confirmation Test conducted from May to July in 2010 was evaluated by external technical specialists at the two meetings of "Technical Committee on Monju Research Utilization", where the core physics tests, plant characteristics tests and component development tests were explained. The committee pointed out the following main points (1) After the 14 year stand-by, the series of tests have successfully completed within 3 months with provision of precious technical data for future FBRs, (2) Safety has been confirmed and valuable data for analysis code validation have been acquired on an FBR core containing 1.5%wt of Am-241. (3) The newly released nuclear data library, JENDL-4.0 has been significantly validated based on studies of capture cross section of Am-241 and of fission cross section of Pu-239. Finally, expectation has been remarked for advancement of Japanese FBR technologies with the JAEA's leadership based of achievements on Monju, to be reflected on subsequent FBRs.
Advanced Nuclear System Research and Development Directorate; Japan Atomic Power Company*
JAEA-Evaluation 2011-003, 303 Pages, 2011/06
JAEA-Evaluation-2011-003.pdf:11.3MBJAEA-Evaluation-2011-003(errata).pdf:0.23MB
JAEA and JAPC launched Fast Reactor Cycle Technology Development Project (FaCT) in 2006. "The Japan Sodium-cooled Fast Reactor (JSFR) with MOX fuel, the advanced aqueous reprocessing, and the simplified pelletizing fuel fabrication systems" have been studied as a main concept in the FaCT project phase-I. In 2010, a judgment on whether the innovative technologies should be adopted was made, and the next R&D programs (phase-II) was proposed. The achievement of the performance targets presented by JAEC was evaluated for the concept of the commercial facilities for FBR cycles, established based on the result of the adoption judgment for the innovative technologies.
FBR Plant Engineering Center; Fast Breeder Reactor Research and Development Center, Tsuruga Head Office; Policy Planning and Co-ordination Department, Tsuruga Head Office
JAEA-Evaluation 2011-004, 132 Pages, 2012/01
JAEA-Evaluation-2011-004.pdf:10.12MB
The logical adequacy of the safety measures in Monju, coolability of the reactor core and the ex-vessel storage tank by natural circulation, and coolability of the spent fuel storage pool, considering Tohoku district - off the Pacific Ocean Earthquake were explained by Japan Atomic Energy Agency and reviewed in the above-titled committee. Main conclusions by the chairman of the committee are summarized as follows: (1) Natural circulation cooling is secured in the reactor after station blackout (SBO) as far as flow path exist. Therefore, the reactor core will never melt because of the decay heat removal as far as the natural circulation is reserved after the reactor shutdown; (2) Spent fuels will never melt due to temperature rise in the ex-vessel fuel storage system, since natural circulation cooling can be expected even after SBO; (3) It is possible to take sufficient countermeasures such as water supply against the spent fuel pool because it takes approximately two month before the top of the spent fuel cans which contain spent fuels are exposed by evaporation of the water.