Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Fast Breeder Reactor Research and Development Center, Tsuruga Head Office
JAEA-Review 2014-030, 138 Pages, 2014/08
The prototype fast breeder reactor Monju has accumulated technical achievements in order to establish the fast breeder reactor cycle technology in Japan using the operation and maintenance experience, etc. This annual report summarizes the primary achievements and the data related to the plant management in Monju during fiscal 2013.
Fast Breeder Reactor Research and Development Center, Tsuruga Head Office
JAEA-Review 2013-032, 172 Pages, 2013/09
The prototype fast breeder reactor Monju has accumulated technical achievements in order to establish the fast breeder reactor cycle technology in Japan using the operation and maintenance experience, etc. This annual report summarizes the primary achievements and the data related to the plant management in Monju during fiscal 2012.
Fast Breeder Reactor Research and Development Center, Tsuruga Head Office
JAEA-Research 2013-001, 392 Pages, 2013/07
Comprehensive safety assessments of MONJU taking into account the accident at Fukushima Dai-ichi Nuclear Power Station of Tokyo Electric Power Company have been performed based on the request of Nuclear and Industrial Safety Agency on July 22, 2011. The assessments focus on earthquake and tsunami as natural phenomena as well as the loss of all alternating current power sources (SBO: Station Blackout) and loss of the ultimate heat sink (LUHS) as the loss of safety functions. Assessed systems are the reactor, the ex-vessel storage tank (EVST) and the spent fuel pool (SFP). The safety margins are assessed by evaluating the scale of events that the plant could withstand against the events beyond design basis without significant damage to the fuel. The ability of natural circulation in primary cooling systems and natural convection of air in the auxiliary air cooling system are taken into account in the assessment for the reactor and the EVST in SBO.
Fast Breeder Reactor Research and Development Center, Tsuruga Head Office
JAEA-Review 2012-032, 187 Pages, 2012/08
FBR Monju has been accumulated technological achievements, for our country of FBR cycle technology, through the experience of daily operation, maintenance, etc.
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
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.
FBR Plant Engineering Center; Fast Breeder Reactor Research and Development Center, Tsuruga Head Office
JAEA-Evaluation 2011-002, 96 Pages, 2011/06
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.