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JAEA Reports

Decommissioning state of Plutonium Fuel Fabrication Facility; Dismantling the glove box W-9 and equipment interior, and a part of tunnel F1

Nagai, Yuya; Shuji, Yoshiyuki; Kawasaki, Takeshi; Aita, Takahiro; Kimura, Yasuhisa; Nemoto, Yasunori*; Onuma, Takeshi*; Tomiyama, Noboru*; Hirano, Koji*; Usui, Yasuhiro*; et al.

JAEA-Technology 2022-039, 117 Pages, 2023/06

JAEA-Technology-2022-039.pdf:11.96MB

Japan Atomic Energy Agency (JAEA) manages wide range of nuclear facilities. Many of these facilities are required to be performed adjustment with the aging and complement with the new regulatory standards and the earthquake resistant, since the Great East Japan Earthquake and the Fukushima Daiichi Nuclear Power Station accident. It is therefore desirable to promote decommissioning of facilities that have reached the end of their productive life in order to reduce risk and maintenance costs. However, the progress of facility decommissioning require large amount of money and radioactive waste storage space. In order to address these issues, JAEA has formulated a "The Medium/Long-Term Management Plan of JAEA Facilities" with three pillars: (1) consolidation and prioritization of facilities, (2) assurance of facility safety, and (3) back-end countermeasures. In this plan, Plutonium Fuel Fabrication Facility has been selected as primary decommissioned facility, and dismantling of equipment in the facilities have been underway. In this report, size reduction activities of the glove box W-9 and a part of tunnel F-1, which was connected to W-9, are presented, and the obtained findings are highlighted. The glovebox W-9 had oxidation & reduction furnace, and pellet crushing machine as equipment interior. The duration of activity took six years from February 2014 to February 2020, including suspended period of 4 years due to the enhanced authorization approval process

Journal Articles

Study of irradiation induced restructuring of high burnup fuel; The New cross-over project (NXO) to study rim-structure formation

Kinoshita, Motoyasu*; Geng, H. Y.*; Chen, Y.*; Kaneta, Yasunori*; Iwasawa, Misako*; Onuma, Toshiharu*; Sonoda, Takeshi*; Yasunaga, Kazufumi*; Matsumura, Sho*; Yasuda, Kazuhiro*; et al.

Proceedings of 2006 International Meeting on LWR Fuel Performance (TopFuel 2006) (CD-ROM), p.248 - 254, 2006/10

The New Crossover Project (NXO) is studying effect of fission irradiation on fuel material that research activity is crossing over universities, national and private laboratories. Simulation studies are being performed to find principal and triggering processes of the rim-structure formation in high burnup LWR fuel pellet, using accelerator irradiation and computational calculations. Accelerator irradiation, high energy electron irradiation, fission energy particle beam and ion implantation (ragegas atoms) and combined overlapping irradiations are being performed. For the target of irradiation, CeO$$_{2}$$ isused as simulation of nuclear fuel. The initial results were such as planar structure made by Oxygen defects created by high energy electrons, and surface modification similar to grain-sub-division created by high fluence high energy particle irradiations.

Oral presentation

Irradiation behavior of FBR MOX fuel pellet with large Pu agglomerate

Maeda, Koji; Sasaki, Shinji; Osato, Yukihiro*; Onuma, Yasuhiro*; Nukaga, Sadayoshi*

no journal, , 

no abstracts in English

Oral presentation

Post irradiation examination of the failure simulation test fuel pins

Sasaki, Shinji; Maeda, Koji; Osato, Yukihiro*; Onuma, Yasuhiro*; Nukaga, Sadayoshi*

no journal, , 

no abstracts in English

Oral presentation

Irradiation behavior of MA-containing MOX fuel, 4; Metallographic examination of Np/Am-MOX fuel irradiated for 10 min. in JOYO

Maeda, Koji; Sasaki, Shinji; Kato, Masato; Kihara, Yoshiyuki; Osato, Yukihiro*; Onuma, Yasuhiro*; Nukaga, Sadayoshi*

no journal, , 

no abstracts in English

Oral presentation

Irradiation behavior of MA-containing MOX fuel, 7; Metallographic examination of Np/Am-MOX fuel irradiated for 24 hours in JOYO

Maeda, Koji; Sasaki, Shinji; Kato, Masato; Kihara, Yoshiyuki; Osato, Yukihiro*; Onuma, Yasuhiro*; Nukaga, Sadayoshi*

no journal, , 

no abstracts in English

Oral presentation

Restructuring and Pu redistribution behavior of JOYO MK-III driver fuel

Maeda, Koji; Sasaki, Shinji; Sekine, Takashi; Osato, Yukihiro*; Onuma, Yasuhiro*; Nukaga, Sadayoshi*

no journal, , 

no abstracts in English

Oral presentation

The Development of a long life control rods in fast ractor, 4; Metallographic examination results of sodium bonded type control rod irradiated in Joyo

Sasaki, Shinji; Maeda, Koji; Soga, Tomonori; Osato, Yukihiro*; Onuma, Yasuhiro*; Nukaga, Sadayoshi*

no journal, , 

no abstracts in English

Oral presentation

High linear power irradiation tests with Am-MOX fuels, 5; Observation of fuel microstructure

Maeda, Koji; Sasaki, Shinji; Katsuyama, Kozo; Donomae, Takako; Osato, Yukihiro*; Onuma, Yasuhiro*; Nukaga, Sadayoshi*

no journal, , 

no abstracts in English

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