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Ichikawa, Shoichi; Haga, Hiroyuki; Katsuyama, Kozo; Uwaba, Tomoyuki; Maeda, Koji; Nishinoiri, Kenji
JAEA-Testing 2012-001, 36 Pages, 2012/07
The life of FBR (Fast Breeder Reactor) fuel assembly is restricted by BDI (Bundle-Duct Interaction). Therefore, it is very important to carry out the out pile bundle compressive tests which can imitate BDI, in order to evaluate BDI behavior. The target of the conventional BDI behavior was thin pins ( 6.5 mm) for fuel pellets which were used with the assembly of Monju (the Monju prototype fast breeder reactor) etc. Furthermore by an upgraded Monju core and a demonstration core, adoption of thick pins for the holler annular pellets is planned. Therefore, it was necessary to carry out BDI evaluation of a thick pin. Then, the plans for out of pile bundle compressive test for large diameter pins were are reported this time.
Ichikawa, Shoichi; Abe, Kazuyuki; Haga, Hiroyuki; Kajima, Hisashi*; Sakurai, Satoshi*; Katsuyama, Kozo; Maeda, Koji; Nishinoiri, Kenji
JAEA-Technology 2011-032, 46 Pages, 2012/01
The assembly technique to the capsular irradiation rig newly developed was established. In the irradiation examination, the assembling disassembling and reassembling to PFB110 "B11(1), B11(2)" and PFB140 "B14" that built in Am-MOX fuel pin was achieved. The reassembly technique by recycling the irradiation material was established in the assembly of B11(2). This time, the assembly and disassembly of B11 (1) were reported. Moreover, the assembly of B14 which improved the assembly technology of B11 (1) was reported.
Kondo, Keietsu; Miwa, Yukio; Tsukada, Takashi; Yamashita, Shinichiro; Nishinoiri, Kenji
Journal of ASTM International (Internet), 7(1), p.220 - 237, 2010/01
no abstracts in English
Kajitani, Yukio; ; Abe, Kazuyuki; Osaka, Masahiko; ; Hirosawa, Takashi; Koyama, Shinichi
PNC TN9440 97-004, 186 Pages, 1997/02
The 25th anniversary meeting of the Alpha-Gamma Facility (AGF) at O-arai Engineering Center of PNC was held on February 7. The AGF started to examine irradiated materials on october 1 and fuel pins irradiated in the Dounreay Fast Reactor, DFR332/2 on December 1, 1971. The contents in this paper of the anniversary meeting are as follows. (1)25 years history and challenging plan for 2000 year. (2)Maintenance logbook of the facility, apparatus and manipulators for 25 years. (3)Recent results of melting temperature, thermal conductivity and lattice constants in irradiated MOX fuels. (4)Development on fission products release measuring apparatus and results of cold run tests. (5)Post irradiated examination results operated at the metallography cell in the Fuels Monitoring Facility (FMF). (6)Development on chemical analysis method for minor actinides (MA) in irradiated MOX fuels. (7)Refurbishment for MA containing MOX fuels, status and specifications for the fabrication and quality control apparatus.
Tachi, Hirokazu; Nishinoiri, Kenji; Hirasawa, Hisao; Uruwashi, Shinichi; Hasegawa, Masahiro
PNC TN9410 88-190, 53 Pages, 1988/01
None
*; *; *; *
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 10n/cm (E0.1 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.
; Usui, Keiji; ;
International Topical Meeting on Nuclear and Hazardous Waste Management (SPECTRUM '94), ,
None
Inoue, Toshihiko; Ogawa, Ryuichiro; Akasaka, Naoaki; Nishinoiri, Kenji
no journal, ,
no abstracts in English
Yamashita, Shinichiro; Akasaka, Naoaki; Nishinoiri, Kenji; Takahashi, Heishichiro
no journal, ,
A modified SUS316 stainless steel (PNC316) for high burn-up fast reactor core application has been successfully developed. The material has a typical composition of 16Cr-14Ni-2.5Mo-0.25P-0.004B-0.1Ti-0.1Nb and is used in the 20% cold-worked condition. To demonstrate irradiation performance of PNC316 cladding irradiation experiments has been successively carried out at the temperature ranging from 775 K to 905 K up to a maximum dose of 125 dpa. In this study, the microstructures of the irradiated specimens were carefully examined. Low-magnification image including some of needle-like precipitates indicates many helium bubbles attaching at the precipitate interface. On the other hand, a representative high-resolution image of the needle-like precipitate with the sizes of a few tens of nanometers long and a few nanometers wide shows a distinct interface structure between FCC matrix and the precipitate. As the results of diffraction pattern and image analyses this characteristic precipitate was identified as FeP phase. Based on the numerous results of TEM examination, it is found that a significant improvement in the swelling resistance of PNC316 was mainly derived from the formation of a stable phosphide that traps helium bubbles and retards the conversion of bubbles to voids.
Nishinoiri, Kenji; Akasaka, Naoaki; Ogawa, Ryuichiro; Inoue, Toshihiko
no journal, ,
In fast reactor, deformation behavior and failure strength of fuel cladding tube (C/T) under loss of coolant flow (LOF) event are important evaluation items of reactor safeties. To evaluate C/T behavior under the primary phase of LOF event, transient bust examination was conducted by neutron irradiated C/T. Specimens of C/T made of PNC316 were irradiated in experimental fast reactor JOYO. In this paper reported the transient burst techniques and the results of the post irradiated examination. In the results, the failure temperature of irradiated C/T has no extreme degradation by comparison of the failure temperature of un-irradiated C/T.
Yamashita, Shinichiro; Sekine, Manabu*; Tachi, Yoshiaki; Akasaka, Naoaki; Nishinoiri, Kenji; Takahashi, Heishichiro
no journal, ,
no abstracts in English
Inoue, Toshihiko; Ogawa, Ryuichiro; Akasaka, Naoaki; Nishinoiri, Kenji
no journal, ,
no abstracts in English