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Kato, Yuko; Umebayashi, Eiji; Okimoto, Yutaka; Okuda, Eiichi; Takayama, Koichi; Ozawa, Takayuki; Maeda, Seiichiro; Matsuzaki, Masaaki; Yoshida, Eiichi; Maeda, Koji; et al.
JAEA-Research 2007-019, 56 Pages, 2007/03
JAEA-Research-2007-019.pdf:6.79MB
In order to resume the System Startup Test (SST) of Monju, replacement fuel have to be loaded in exchange for some of initial fuel now loaded in the core to compensate core reactivity lost by decay of Pu-241 in them. The replacement fuel were being stored either in sodium in an ex-vessel storage tank or in air in a storage rack for about 10 years since their fabrication. The initial fuel were irradiated during the SST which was suspended in the end of 1995 and then stayed being loaded in the sodium-circulated core. As this long-term storage and loading may deteriorate mechanical integrity of the assemblies, a study has been made thoroughly on its thermal-hydraulic, structural and material effects on them that might be caused by irradiation in the core, sodium and mechanical environment. The study has shown that the mechanical integrity of them is well maintained even with this long-term storage and loading.
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PNC TN9410 85-140, 72 Pages, 1985/05
Postirradiation Examination (PIE) of "JOYO" MK-II core fuel subassembly (Fab. No. PFD003) has been performed. The purposes of the PIE were to eonfirm the safety performance of the subassembly in reactor "JOYO" at 100MW reactor power, and to get the basic data on the irradiation behavior of MK-II core fuel subassembly and its fuel elements in the early stage of 100MW power operation. The average burnup of the subassembly is estimated to 13,300MWD/MTM. The results of the present examination can be summarized below: (1)There was no pin failure and/or damages in the subassembly, and the subassembly and its fuel elements have behaved normally in reactor, (2)The observation on fuel pin and wire surfaces indicated a slight "contact mark". The size of the mark were very small both in width and in length. The extent of the contact mark is nearly the same as the preceding subassembly [PFD010]. (3)It was confirmed that there was no significant irradiation behavior in the subassembly and its fuel elements.
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PNC TN9410 85-133, 64 Pages, 1985/02
Postirradiation Examination (PIE) of "JOYO" MK-II Structural Materials Irradiation Rig (SMIR : Fab. No. PRS040) has been performed. The rig was irradiated during the 1st cycle of 100MW reactor power, and had the neutron fluence of about 1.19 
10
n/cm
(E
0.1 MeV) The purpose of the present PIE in Fuel Monitoring Facility (FMF) are listed as following: (1)Verification of validity of designing of the integrity and investigation on irradiation behavior of "SMIR". (2)Evaluation of the propriety of the "SMIR" designing from a viewpoint of the disassembling and sodium removal. (3)The handling of small test pieces and shipment of the test pieces to Materials Testing in MMF. The result were summarized as follows : (1)Neutron fluence of "SMIR" was relctivey low, so that the integrity and rig elements were kept normelly during irradiation period. (2)The residual sodium in the rig was scarcely found, and the rig was easily disassembled by remote handling. (3)The remote handling of small test pieces was easily carried out. A standard schedule for "SMIR" PIE performance in FMF has been established.
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PNC TN9410 84-127, 79 Pages, 1984/11
Postirradiation Examination (PIE) of "JOYO" MK-II core fuel sub-assembly (Fab.No.PFD010) has been performed. This subassembly was the first one which subjected to PIE in Fuel monitoring Facility (FMF). The purposes of the PIE were to confirm the safty performance of the subassembly in reactor "JOYO" at 100 MW reactor power, and to get the basic data on the irradiation behavior of MK-II core fuel subassembly and its fuel elements in the early stage of 100MW power operation. The average burnup of the subassembly is estimated to 4600 MWD/MTM. The results of the present examination can be summarized below (1)There was no pin failure and/or damages in the subassembly, and the subassembly and its fuel elements have behaved normally in reactor. (2)The observation on fuel pin and wire surfaces indicated a slight "contact mark". The size of the mark were very small both in width and in length. They seem to be different from those of wear mark observed on MK-I fuel pins. (3)It was confirmed that there was no significant irradiation behavior in the subassembly and its fuel elements.
Okawachi, Yasushi; Kitano, Akihiro; Suzuki, Takayuki; Okimoto, Yutaka; Usami, Shin; Deshimaru, Takehide
no journal, ,
no abstracts in English
Kato, Yuko; Miyagawa, Takayuki; Kageyama, Takeshi; Okimoto, Yutaka
no journal, ,
no abstracts in English
Okawachi, Yasushi; Kitano, Akihiro; Suzuki, Takayuki; Okimoto, Yutaka; Usami, Shin; Deshimaru, Takehide
no journal, ,
no abstracts in English
Kato, Yuko; Miyagawa, Takayuki; Kageyama, Takeshi; Okimoto, Yutaka
no journal, ,
no abstracts in English