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Kurihara, Momo*; Yasutaka, Tetsuo*; Aono, Tatsuo*; Ashikawa, Nobuo*; Ebina, Hiroyuki*; Iijima, Takeshi*; Ishimaru, Kei*; Kanai, Ramon*; Karube, Jinichi*; Konnai, Yae*; et al.
Journal of Radioanalytical and Nuclear Chemistry, 322(2), p.477 - 485, 2019/11
Times Cited Count：2 Percentile：21.58(Chemistry, Analytical)We assessed the repeatability and reproducibility of methods for determining low dissolved radiocesium concentrations in freshwater in Fukushima. Twenty-one laboratories pre-concentrated three of 10 L samples by five different pre-concentration methods (prussian-blue-impregnated filter cartridges, coprecipitation with ammonium phosphomolybdate, evaporation, solid-phase extraction disks, and ion-exchange resin columns), and activity of radiocesium was measured. The z-scores for all of the 
Cs results were within 
2, indicating that the methods were accurate. The relative standard deviations (RSDs) indicating the variability in the results from different laboratories were larger than the RSDs indicating the variability in the results from each separate laboratory.
spent fuel and ATR MOX spent fuelShirai, Nobutoshi; Inano, Masatoshi; Fukuda, Kazuhito; Kosaka, Ichiro; Yamanaka, Atsushi
JAEA-Research 2011-005, 95 Pages, 2011/03
JAEA-Research-2011-005.pdf:2.46MB
This report presents criticality safety evaluation of each equipment in Tokai Reprocessing Plant for two types of spent fuels, High burn up 4.2% enrichment U oxide spent fuel for light water reactor and U-Pu mixed oxide spent fuel for advanced thermal reactor. As a result, it was confirmed that the equipments were safe enough for two types of the spent fuels from view point of criticality safety of single unit and multiple units.
spent fuel and ATR MOX spent fuel in Tokai Reprocessing PlantShirai, Nobutoshi; Inano, Masatoshi; Fukuda, Kazuhito; Kosaka, Ichiro; Yamanaka, Atsushi
JAEA-Research 2011-004, 60 Pages, 2011/03
JAEA-Research-2011-004.pdf:1.79MB
This report describes calculated results of inventory of radioactivity in the Tokai Reprocessing Plant with calculation code, based on initial conditions and nuclear data library. The inventories were compared with three types of spent fuels, High burn up U oxide for light water reactor, U-Pu mixed oxide for advanced thermal reactor and the design based fuel for Tokai Reprocessing Plant.
Shirai, Nobutoshi; Inano, Masatoshi
JAEA-Data/Code 2006-002, 5 Pages, 2006/03
JAEA-Data-Code-2006-002.pdf:0.49MB
This report describes basic data related to civil engineering, construction, operation, electric power, steam, chemical reagents and radioactive wastes of Tokai Reprocessing Plant for environmental burden evaluation.
spent fuel and ATR MOX spent fuel in Tokai reprocessing plantShirai, Nobutoshi; Inano, Masatoshi
JAEA-Research 2005-001, 7 Pages, 2005/11
JAEA-Research-2005-001.pdf:0.31MB
This report describes calculated results of inventory of radioactivity in the Tokai Reprocessing Plant with calculation code, based on initial conditions and nuclear data library. The inventories were compared with two types of spent fuels, U oxide for light water reactor and U-Pu mixed oxide for advanced thermal reactor.
Nomura, Shigeo; Kikuchi, Ko; Omori, Eiichi; Inano, Masatoshi
Enerugi, 38(6), p.59 - 62, 2005/00
None
Takafumi, Nakano,; Ishida, Michihiko; Kazuyuki, Morimoto,; Inano, Masatoshi; Nojiri, Ichiro
JNC TN8410 2003-017, 190 Pages, 2004/03
JNC-TN8410-2003-017.pdf:6.61MB
Probabilistic Safety Assessment (PSA) methodology has been applied to evaluate the relative importance of safety functions that prevent the progress of event causing to postulate accidents.
Totsuka, Masayoshi; Shirai, Nobutoshi; Takaya, Akikazu; Inano, Masatoshi
no journal, ,
no abstracts in English
Ishida, Michihiko; Inano, Masatoshi; Suzuki, Kazuhiko*
no journal, ,
no abstracts in English
Sato, Yoshihiko; Sato, Soichi; Inano, Masatoshi; Kimura, Arata*; Miyake, Atsumi*; Ogawa, Terushige*
no journal, ,
no abstracts in English
Takaya, Akikazu; Mizuniwa, Naoki; Tanabe, Yoji; Sato, Soichi; Inano, Masatoshi
no journal, ,
no abstracts in English
Ishida, Michihiko; Suto, Toshiyuki; Inano, Masatoshi; Aoshima, Atsushi
no journal, ,
In the Tokai Reprocessing Plant (TRP), process safety has been evaluated since the fire and explosion incident of the bituminization facility in 1997. In this report, both deterministic and probabilistic safety assessment approaches of the TRP are summarized.
Ishida, Michihiko; Suto, Toshiyuki; Inano, Masatoshi; Aoshima, Atsushi; Muramatsu, Ken; Ueda, Yoshinori*
no journal, ,
A study to evaluate component failure rates for a reprocessing plant has started at the Japan Atomic Energy Agency (JAEA). The study is sponsored by the Japan Nuclear Energy Safety Organization (JNES) as a contract research. The Tokai Reprocessing plant(TRP) has been operating over 30 years since 1977. Maintenance records of plant components have been accumulated and compiled in the Tokai Reprocessing Plant Maintenance Support System (TORMASS). Since the TORMASS was thought to be an effective source to pick up component failure information, the evaluation work of component failure rates started at 2005 based on the maintenance records in the TORMASS. By the end of 2006, failure rates for 17 types of 392 components had been evaluated. This result is expected to contribute to building up generic database for reprocessing plant component failure rates in order to promote the utilization of the risk information for reprocessing plants in Japan.
Ishida, Michihiko; Inano, Masatoshi; Aoshima, Atsushi; Suto, Toshiyuki; Muramatsu, Ken; Ueda, Yoshinori*
no journal, ,
Component failure rates are one of the most important inputs for PSA. Although there are many component failure rates databases for NPPs, there are few for a reprocessing plant. Therefore, in order to perform reliable PSA of a reprocessing plant, it is important to establish the failure rate database based on the actual plant maintenance data. The Tokai Reprocessing Plant (TRP) has been operating over 30 years since 1977. Maintenance records of plant components have been accumulated and compiled in the Tokai Reprocessing Plant Maintenance Support System (TORMASS). A basic study has started in the JAEA from 2005 by using the TORMASS data to contribute the development of reliable component failure rates. The outlines of the component failure estimation are summarized.
Nakano, Takafumi; Inano, Masatoshi; Aoshima, Atsushi
no journal, ,
no abstracts in English
