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.

Summary of typical routine maintenance activities at Tokai reprocessing plant

; ; ;

JNC TN8450 2001-006, 861 Pages, 2001/09

JNC-TN8450-2001-006.pdf:34.98MB

Typical maintenance activities, such as replacement of worn out parts and cleaning of filter elements, routinely performed during steady operation are summarized. The purpose of this summary is to give elementary understanding on these activities to people who are responsible for explain them to the public. This summary also includes glossary and flow diagram with basic data.

Summary of typical routine maintenance activities at Tokai reprocessing plant

; ; ;

JNC TN8450 2000-006, 700 Pages, 2000/09

JNC-TN8450-2000-006.pdf:14.6MB

Typical maintenance activities, such as replacement of worn out parts and cleaning of filter elements, routinely performed during steady operation are summarized. The purpose of this summary is to give elementary understanding on these activities to people who are responsible for explain them to the public. This summary also includes glossary and flow diagram with basic data.

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JNC TN9200 99-005, 17 Pages, 1998/12

JNC-TN9200-99-005.pdf:1.92MB

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; ; Miyazaki, Hitoshi; ; Tanimoto, Kenichi; Terunuma, Seiichi

PNC TN9420 95-011, 13 Pages, 1994/10

PNC-TN9420-95-011.pdf:8.44MB

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; Miyazaki, Hitoshi; ; Tanimoto, Kenichi; Terunuma, Seiichi

PNC TN9420 94-010, 103 Pages, 1994/04

PNC-TN9420-94-010.pdf:2.89MB

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Development of Decommissioning Technologies for Nuclear Fuel Cycle Facilities in PNC

; Enokido, Yuji;

Proceedings of 2nd ASME-JSME International Conference on Nuclear Engineering (ICONE-2), p.813 - 819, 1993/00

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The gamma irradiation experiment of simulated groundwater related the geologic disposal of high level waste

; ; ; Tanimoto, Kenichi; Enokido, Yuji

PNC TN9410 92-208, 68 Pages, 1992/07

PNC-TN9410-92-208.pdf:1.55MB

The plan of the gelogic disposal of high level waste that need to do estimate the effect of radiation in near field surrouding waste. We have applied "JOYO" spent fuel storage pool as irradiation field and investigated the effect of gamma radiation about quality of groundwater, because we have to obtained a basic data related geologic dispose under irradiaton condition. The experiment was applied artificial brine for simulated groundwater. The same samples were located in "JOYO" spent fuel storage pool without gamma radiation and other effects were estimated. The samples were also observed the variation of quality of artifical brine every fixed time after irradiation and were estimated the effect as the function of time, gamma irradiation were carried out from 24hours (1.0101.310Gy) to 1440 hours (4.410 6.810Gy). The results indicate the following. (1)The change of pH, conductivity and ion concentrations in artifical brine could not be observed in the samples before and after irradiation. (2)Eh of the samples was 241mV before irradiation, but it decreased 156mV after irradiaton for 1440 hours. Eh tend to decrease by increase of the absorption dose. (3)Do of the samples before and after irradiation for 1440 hours were 20.76 and 5930 g/, respectively. Do tend to increases by increase of the absorption dose. (4)Before and after irradiation test for 480 hours, nitric ion was detected 2.9 and 105ppm, respectively, In no gamma irradiaton test, nitric ion was detdcted 4.0 and 5.6ppm, respectively. For 1440 hours, nitric ion was detected 15ppm after irradiation and 11ppm after rest without gamma irradiation. (5)pH, Eh, Do, conductivity and all ion concentrations in artifical brine have no the variation as the function ot time within fixed time (about 4hours) after irradiation. These results suggest that oxygen which were generated by the gamma radiolysis of water was incrased Do, ...

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; Nakano, Tomoyuki; ; ; Asami, Makoto*; Tanimoto, Kenichi; Enokido, Yuji

PNC TN9080 92-001, 107 Pages, 1992/01

PNC-TN9080-92-001.pdf:2.24MB

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; ; ; ; ; Usami, Tomoyuki

PNC TN9510 91-003, 40 Pages, 1991/08

PNC-TN9510-91-003.pdf:1.06MB

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