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JAEA Reports

Consideration on the earthquake-resistant margin of equipment base-bolts receiving the shearing load during seismic movements

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.

Oral presentation

Emergency safety measures at the Tokai Reprocessing, 2

Ouchi, Masayuki; Hoshi, Takahiro; Sasaki, Shunichi; Isobe, Hiroyasu; Nagaoka, Shinichi; Kurabayashi, Kazuaki; Obu, Tomoyuki

no journal, , 

Plutonium nitrate solution is stored in tanks that have cooling system to prevent boiling accident by decay heat and scavenging system to prevent explosion of hydrogen generated by radiolysis. These systems are designed to be provided power from emergency power generators at the Tokai Reprocessing Plant (TRP) when commercial power is lost. In addition, some apparatus (mobile power generators and nitrogen gas cylinder to scavenge hydrogen, etc.) are recently deployed at TRP on the basis of power loss in Fukushima Daiichi nuclear accident. In this report, these safety measures for emergency are shown.

Oral presentation

Measurement of the hydrogen concentration in the vessel off-gas generated radiolytically from Pu storage tanks

Hoshi, Takahiro; Nagaoka, Shinichi; Kudo, Atsunari; Ouchi, Masayuki; Isobe, Hiroyasu; Obu, Tomoyuki; Kurabayashi, Kazuaki

no journal, , 

no abstracts in English

Oral presentation

MOX reprocessing at TRP, 7; Behavior of Iodine-131 from high active waste storage in Tokai Reprocessing Plant

Shirato, Yoji; Yamanaka, Atsushi; Tsutagi, Koichi; Yoshino, Yasuyuki; Kishi, Yoshiyuki; Isobe, Hiroyasu

no journal, , 

no abstracts in English

Oral presentation

Corrosion evaluation of uranium evaporator made of Ti in the Tokai Reprocessing Plant

Shirato, Yoji; Isozaki, Toshihiko; Kishi, Yoshiyuki; Isobe, Hiroyasu; Nakamura, Yoshinobu; Uchida, Toyomi; Seno, Shigeo

no journal, , 

no abstracts in English

Oral presentation

Flush-out for Tokai Reprocessing Plant decommissioning, 4; Removal of the U solution

Ouchi, Masayuki; Samoto, Hirotaka; Kishi, Yoshiyuki; Isobe, Hiroyasu; Yasuda, Takeshi; Yada, Yuji; Suzuki, Shohei; Tokoro, Hayate; Kusaka, Shota; Shoji, Keita

no journal, , 

Tokai Reprocessing Plant (TRP) retained nuclear materials such as spent fuel sheared powder, plutonium solution, and uranium solution due to TRP shift to decommissioning in anticipation of resuming reprocessing. Flush-out to sequentially remove these nuclear fuel materials was required for future decommissioning of equipment. U solution was denitrified to UO$$_{3}$$ powder as the final stage of flush-out, stored in the uranium storage. We performed inspections and training, simultaneously transferring technical knowledge to young engineers. Safe and stable processing was achieved by establishing conditions that could treat lower-concentration U solution and prevent nozzle clogging. Additionally, by denitrifying the diluted U solution in the feed tank, the washing waste was significantly reduced. Through these efforts, flush-out for TRP was successfully completed.

Oral presentation

Flush-out for Tokai Reprocessing Plant decommissioning, 3; Disposal of the low-concentration Pu solution

Yanagibashi, Futoshi; Nagaoka, Shinichi; Isobe, Hiroyasu; Yasuda, Takeshi; Yada, Yuji; Suzuki, Shohei; Tokoro, Hayate; Kusaka, Shota; Shoji, Keita; Samoto, Hirotaka

no journal, , 

Tokai Reprocessing Plant (TRP) retained nuclear materials, such as low-concentration Pu solution due to TRP's shift to decommissioning in anticipation of resuming reprocessing. Pu solution required disposal as Flush-out before decontamination of equipment. Considering the operational range, the processing period, and the utilization after processing, Pu solution was transferred to high-active liquid waste tanks without evaporation or MOX conversion. During transferring, there was a critical risk due to Pu polymer formation caused by increasing in liquid temperature and decreasing in acid concentration. Based on past experience, U solution was mixed before transfer, and the acid concentration of the receiving tanks was adjusted. These measures prevented Pu polymer formation, ensured critical safety, and completed the disposal of low-concentration Pu solution.

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