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Shirai, Nobutoshi; Miura, Yasushi; Tachibana, Ikuya; Omori, Satoru; Wake, Junichi; Fukuda, Kazuhito; Nakano, Takafumi; Nagasato, Yoshihiko
JAEA-Technology 2016-007, 951 Pages, 2016/07
JAEA-Technology-2016-007-01.pdf:11.93MBJAEA-Technology-2016-007-02.pdf:4.7MB
The periodic safety review of TRP is to confirm the safety activities and get effective additional measures the facility safety and its reliability. We implemented 4 items; for (1) evaluation of safety activity implementation, we confirmed we are adequately expanding its safety activities by the necessary documents and schemes. For (2) evaluation of status of safety activities reflecting the latest technical knowledges, we confirmed we reflect latest knowledges for improvement of safety and reliability. For (3) technical evaluation about aging degradation, we can keep the safety of the facilities important to safety and the sea discharge line, under assumption of the present maintenance, because of "focuses for aging degradation". For (4) planning measures about a 10-years-plan that the operator shall implement to keep the facility condition, by the technical evaluation, we found no additional safety plans into maintenance strategies.
Sakaguchi, Shinobu; Tachibana, Ikuya; Koshino, Katsuhiko; Shirozu, Hidetomo; Shirai, Nobutoshi; Imamoto, Nobuo; Tomita, Tsuneo; Tobita, Hiroo; Yamanaka, Atsushi; Kobayashi, Daisuke; et al.
JAEA-Technology 2011-006, 24 Pages, 2011/03
JAEA-Technology-2011-006.pdf:3.07MB
In the Niigataken Chuetsu-oki Earthquake on 2007, observed earthquake motion exceeded design base at the Kashiwazaki Kariwa nuclear plant. However, there was no earthquake damage in safety important equipments to stop reactor, to cool reactor, and to contain radioactive materials. One of this reason is said that many safety margin are included in the design and the permissible value. To know more accurate safety margin, shearing force examinations for the base bolts were conducted. In examinations, delegate test-bolts were made; the test bolts were selected from heavier equipment in Tokai Reprocessing Plant. In this report, the shearing strength obtained from the examinations shows more accurate safety margin.
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.
Shirai, Nobutoshi; Sudo, Toshiyuki; Nojiri, Ichiro
Monte Karuroho Niyoru Ryoshi Shimyureshon No Genjo To Kadai, p.235 - 249, 2002/00
None
Shirai, Nobutoshi; ; ; Shirozu, Hidetomo; Sudo, Toshiyuki; Hayashi, Shinichiro;
JNC TN8410 2000-006, 116 Pages, 2000/04
JNC-TN8410-2000-006.pdf:2.77MB
Criticality limits for equipments in Tokai Reprocessing Plant which handle fissile material solution and are under shape and dimension control were reevaluated based on the guideline No.10 "Criticality safety of single unit" in the regulatory guide for reprocessing plant safety. This report presents criticality safety evaluation of each equipment as single unit. Criticality safety of multiple units in a cell or a room was also evaluated. The evaluated equipments were ones in dissolution, separation, purification, denitration, Pu product storage, and Pu conversion processes. As a result, it was reconfirmed that the equipments were safe enough from a view point of criticality safety of single unit and multiple units.
Shirai, Nobutoshi; Taguchi, Katsuya; Iitsuka, Shoji; ; *; Sudo, Toshiyuki
JNC TN8410 99-055, 69 Pages, 1999/09
As a part of the safety confirmation work of Tokai Reprocessing Plant, an assessment of the basic data for criticality safety and shielding design has already been reported. In that report, two plutonium solution storage cells were evaluated to be safe enough from a viewpoint of multiple unit criticality safety. In this report, additionai evaluation of multiple unit criticality safety was made for the main plant and the UO
storage which were designed in 1960's and constructed in 1970's. The evaluated cells and rooms are enriched uranium dissolution cell, adjustment and feeding cell, two second extraction cycle cells, third uranium cycle cell, uranium concentration and denitration rooms, third plutonium cycle cell, plutonium concentration cell, two plutonium solution storage cells, rework cell, and UO storage room. As a result, it was confirmed that these cells and rooms were safe enough from a viewpoint of multiple unit criticality safety.
Shirai, Nobutoshi; Sudo, Toshiyuki
PNC TN8460 95-001, 92 Pages, 1995/09
no abstracts in English
Sudo, Toshiyuki; Shirai, Nobutoshi
PNC TN8450 95-009, 26 Pages, 1995/09
This report presents the results of criticality benchmark calculations performed to validate the SCALE-4 code system for Pu-U mixtures with low Pu content (less than 10wt.%) on the assumption that the SCALE is applied to the criticality safety analysis for nuclear fuel facilities handling LWR-MOX fuels. The SCALE-PC 4.1 on a personal computer and the SCALE 4.2 on a SUN EWS were used. The number of the calculated cases are 11 for homogeneous MOX systems, 13 for Pu-U nitrate solutions, and 57 for heterogeneous MOX fuel pin systems, sums up to 81. The calculation results show that there are no significant differences between the results from SCALE-PC 4.1 and SCALE 4.2 calculations. Maximum, minimum, and average k-effectives calculated by SCALE 4.2 are 0.993, 1.026, and 1.005 respectively. The average k-effectives for the critical systems mentioned above are 1.015
0.006, 1.0110.003, and 1.0010.004 respectively, which indicates that SCALE-4 can accurately predict the k-effective for Pu-U mixtures with low Pu content.
Totsuka, Masayoshi; Shirai, Nobutoshi; Takaya, Akikazu; Inano, Masatoshi
no journal, ,
no abstracts in English
Fukuda, Kazuhito; Tomioka, Kenichiro*; Tachibana, Ikuya; Shirai, Nobutoshi; Kosaka, Ichiro; Nakano, Takafumi; Nagasato, Yoshihiko
no journal, ,
no abstracts in English
Koshino, Katsuhiko; Shirai, Nobutoshi; Sakaguchi, Shinobu; Shirozu, Hidetomo; Otaki, Miyuki*; Kosaka, Ichiro; Nakano, Takafumi; Nagasato, Yoshihiko; Tachibana, Ikuya
no journal, ,
no abstracts in English