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JAEA Reports

Tritium removal of heavy water system and helium system in FUGEN

Takiya, Hiroaki; Kadowaki, Haruhiko; Matsushima, Akira; Matsuo, Hidehiko; Ishiyama, Masahiro; Aratani, Kenta; Tezuka, Masashi

JAEA-Technology 2020-001, 76 Pages, 2020/05

JAEA-Technology-2020-001.pdf:6.06MB

Advanced Thermal Reactor (ATR) FUGEN was operated for about 25 years, and now has been proceeding decommissioning after the approval of the decommissioning plan in Feb. 2008. The reactor, heavy water system and helium system are contaminated by tritium because of neutron absorption of heavy water, which is a moderator. Before dismantling these facilities, it is necessary to remove tritium from them for not only reducing the amount of tritium released to surrounding environment and the risk of internal exposure by tritium but also ensuring the workability. In first phase of decommissioning (Heavy Water and Other system Decontamination Period), tritium decontamination of the reactor, heavy water system and helium system started in 2008 and completed in 2018. This report shows the results of tritium decontamination of the reactor, heavy water system and helium system.

Journal Articles

Site occupancy of interstitial deuterium atoms in face-centred cubic iron

Machida, Akihiko; Saito, Hiroyuki; Sugimoto, Hidehiko*; Hattori, Takanori; Sano, Asami; Endo, Naruki*; Katayama, Yoshinori; Iizuka, Riko*; Sato, Toyoto*; Matsuo, Motoaki*; et al.

Nature Communications (Internet), 5, p.5063_1 - 5063_6, 2014/09

 Times Cited Count:55 Percentile:86.02(Multidisciplinary Sciences)

Iron hydride FeH$$_x$$, is thermodynamically stable only at high hydrogen pressure of several GPa. To investigate the hydrogenation process and hydrogen state in iron hydride, it is necessary to carry out the in-situ measurement under high pressure and high temperature. In this study, we performed the in-situ neutron diffraction measurement of Fe-D system using the high pressure neutron diffractometer PLANET in the MLF, J-PARC, and determined the deuterium occupying sites and occupancies in fcc-FeD$$_x$$. We found the minor occupation of tetrahedral sites under high pressure and high temperature. We considered the mechanism of the minor occupation based on the Quantum-mechanical calculation.

Oral presentation

Technology development for decommissioning in FUGEN and current status

Kitamura, Koichi; Sano, Kazuya; Nakamura, Yasuyuki; Matsushima, Akira; Matsuo, Hidehiko; Ishiyama, Masahiro; Haneda, Takahiro; Tezuka, Masashi

no journal, , 

The decommissioning program of proto-type Advanced Thermal Reactor (ATR) FUGEN has started in 2008 as first decommissioning of the commercial-scale water reactor. It consists of four periods, considering the transportation of spent fuels and the radioactive decrease of highly activated materials. It is expected that the whole program of decommissioning will be completed until 2028.Now, the decommissioning is under the first period, spent fuels and heavy water has been carrying out from FUGEN, and a part of the turbine system with relatively low radioactive contamination has been dismantled. FUGEN has a complicated core structure consisting 224 fuel channels with pressure tubes and calandria tank, etc. and used heavy water as moderator, unlike other light water reactor. So, the dismantling technology of the reactor core and the decontamination technology of tritium in heavy water system, etc. have been studying in order to dismantle them safely. In this presentation, the contents of the decommissioning program and its current status, the studying situation of dismantling technology of reactor core using Abrasive Water Jet (AWJ) which is a candidate of cutting technologies, the examination of tritium decontamination in heavy water system, the study for C-14 penetrated into concrete structure will be presented mainly.

Oral presentation

Current status of the decommissioning of FUGEN

Katano, Yoshiaki; Matsuo, Hidehiko

no journal, , 

no abstracts in English

Oral presentation

Tritium removal test for decommissioning of FUGEN

Matsushima, Akira; Ishiyama, Masahiro; Matsuo, Hidehiko; Sato, Yuji

no journal, , 

no abstracts in English

Oral presentation

Study of removal technique and confirmation technique of removal condition in heavy water withdraw and tritium removal for decommissioning of FUGEN

Kadowaki, Haruhiko; Matsuo, Hidehiko; Yamane, Naoki; Matsushima, Akira

no journal, , 

no abstracts in English

Oral presentation

A Tritium removal for the decommissioning of FUGEN, 1; Applicability of the tritium removal technique for the actual equipment and pipe

Ando, Koji; Kadowaki, Haruhiko; Matsuo, Hidehiko; Yamane, Naoki; Matsushima, Akira

no journal, , 

no abstracts in English

Oral presentation

Tritium removal of FUGEN using a compact portable dehumidifier system of hollow fiber membrane separation, 2; Verification test of applicability

Kadowaki, Haruhiko; Matsuo, Hidehiko; Yamane, Naoki; Asakura, Yamato*; Matsushima, Akira

no journal, , 

no abstracts in English

Oral presentation

The Tritium removal for the decommissioning of FUGEN, 2; Estimation of amount of residual heavy water

Miyoshi, Nobuaki; Kadowaki, Haruhiko; Matsuo, Hidehiko; Matsushima, Akira

no journal, , 

no abstracts in English

Oral presentation

Trial of fixed and removable metal mesh filter

Matsuo, Hidehiko; Iwai, Masaki

no journal, , 

no abstracts in English

Oral presentation

Technology development for the reactor dismantling in Fugen, 2-1; Strategy for the sampling from the reactor structure and demonstration of the elemental technology

Iwai, Hiroki; Nakamura, Yasuyuki; Matsuo, Hidehiko; Mizui, Hiroyuki; Sano, Kazuya

no journal, , 

no abstracts in English

Oral presentation

Technology development for the reactor dismantling in Fugen, 2-2; Development of the sampling device for reactor structure

Matsuo, Kimihiko*; Ishitobi, Tatsuhiko*; Oka, Hiroshi*; Iwai, Hiroki; Matsuo, Hidehiko; Nakamura, Yasuyuki; Sano, Kazuya

no journal, , 

no abstracts in English

Oral presentation

Maintenance of reactor facilities under decommissioning in FUGEN

Hayashi, Kenta; Ito, Kenji; Matsuo, Hidehiko; Sakai, Yasuhiro

no journal, , 

no abstracts in English

Oral presentation

Including spaces rational maintenance plan on decommissioning in FUGEN

Yamamoto, Takashi; Matsuo, Hidehiko; Miyashita, Shinichi

no journal, , 

Fugen is a heavy water-moderated, boiling light water-cooled, pressure tube-type reactor with the electrical power of 165 MW. It had been operated for 25 years from March 1979 to March 2003. After ceasing its operation, decommissioning project started 2008. Currently, FUGEN is the second phase of decommissioning (Reactor Periphery Facilities Dismantling Period). Fugen in decommissioning has the risk decreased than in operation. Therefore, it have been rationalizing maintenance continuously. At the paper, report on the rationalization and improvements of the maintenance in decommissioning. After ceasing the operation, all of the spent fuels were removed from reactor to the spent fuel pool. And now, the spent fuels has low heat generation and it is not necessary to remove the heat. Therefore, we are continuing to rationalize the maintenance plan depending on the situation of decommissioning.

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