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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
Tachi, Hirokazu; Nishinoiri, Kenji; Hirasawa, Hisao; Uruwashi, Shinichi; Hasegawa, Masahiro
PNC TN9410 88-190, 53 Pages, 1988/01
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
Konno, Shotaro; Takaya, Shigeru; Nagae, Yuji; Yamagata, Ichiro; Ogawa, Ryuichiro; Akasaka, Naoaki; Nishinoiri, Kenji
no journal, ,
We are developing a method for evaluation of irradiation damage of structural materials in nuclear plants by using change in magnetic flux density due to irradiation damage. In this study, the magnetic flux density measurement technique has been improved by introducing a new magnetizer which enables local magnetizing by contacting the sample surface. We can magnetize samples, especially ferromagnetic samples, more precisely compared to the existing method. Furthermore, the new method provided the path for the application to real plants.
Inoue, Toshihiko; Ogawa, Ryuichiro; Akasaka, Naoaki; Nishinoiri, Kenji
no journal, ,
no abstracts in English
Konno, Shotaro; Takaya, Shigeru; Nagae, Yuji; Yamagata, Ichiro; Ogawa, Ryuichiro; Akasaka, Naoaki; Nishinoiri, Kenji
no journal, ,
We are developing a method for evaluation of irradiation damage on structural materials in nuclear plants by using change in magnetic flux density due to irradiation damage. In this study, the magnetic flux density measurement technique has been improved by introducing a new magnetizer which enables local magnetizing by contacting the sample surface, and the calibration method of the flux gate sensor for the magnetic flux density. We can magnetize samples, especially ferromagnetic samples, more precisely compared to the existing method. Furthermore, the new method can remove many limitations for the application to real plants.
Sekio, Yoshihiro; Yamashita, Shinichiro; Yoshitake, Tsunemitsu; Nishinoiri, Kenji; Takahashi, Heishichiro*
no journal, ,
In this study, microstructural observation of Fe-15Cr-15Ni ternary model alloy and PNC316 irradiated in JOYO was performed to clarify the defect accumulation process in the vicinity of grain boundary and also the relationship between grain boundary coherency and the void structure developing process was evaluated. As the result of microstructural observation, the followings are obtained; void denuded zone (VDZ) was developed in the vicinity of the low symmetry grain boundary of Fe-15Cr-15Ni whereas no VDZ developed in the vicinity of high symmetry grain boundary. In the case of PNC316, narrow VDZ was developed only at the low symmetry grain boundary.
Yamashita, Shinichiro; Yano, Yasuhide; Otsuka, Satoshi; Kaito, Takeji; Akasaka, Naoaki; Inoue, Masaki; Yoshitake, Tsunemitsu; Nishinoiri, Kenji; Koyama, Shinichi; Tanaka, Kenya
no journal, ,
In this work, neutron irradiation behaviour of ODS ferritic steel cladding tubes developed for fast reactor (FR) was investigated to understand the effect of neutron irradiation on their microstructures. Chemical compositions of the ODS cladding tubes examined were Fe-0.13C-8.84Cr-1.97W-0.20Ti-0.34YO(9Cr-ODS) and Fe-0.04C-11.34Cr-1.89W-0.25Ti-0.23YO (12Cr-ODS). These ODS cladding tubes were irradiated, without fuel condition, at 731-1089 K to fast fluences ranging from 3.2 to 6.610 n/m (E 0.1 MeV) in the experimental fast reactor JOYO. Microstructural stability of these cladding tubes was evaluated using transmission electron microscope (TEM). Density of the tube specimens before and after irradiation was measured by a conventional immersion method with water, indicating that no significant swelling occurred for all the irradiated specimens. TEM observations show that the radiation-induced defect cluster formation during neutron irradiation was suppressed. It was highly possible due to high density defect sink site such as initially-existed dislocation introduced during tube fabrication process, interface between precipitates including oxide and each matrix. In addition, it revealed that oxide particles, which are closely related with high temperature strength under the practical reactor operation, were stable up to the maximum doses of this irradiation test from the analyses of TEM micrographs.
Kondo, Keietsu; Nakano, Junichi; Tsukada, Takashi; Yamashita, Shinichiro; Nishinoiri, Kenji
no journal, ,
no abstracts in English
Sekio, Yoshihiro; Yamashita, Shinichiro; Yoshitake, Tsunemitsu; Nishinoiri, Kenji; Takahashi, Heishichiro
no journal, ,
The process of the irradiation-induced defects accumulation during irradiation has not been clarified yet, namely what microstructural factors affect defect accumulation process. For this reason, we investigated the void distribution near grain boundaries by focusing on grain boundaries as a microstructural factor in Fe-15Cr-15Ni model alloy and PNC316 stainless steel used for the nuclear fast reactor. It was clarified that the void denuded zone were formed near only a random grain boundary under neutron irradiation in Fe-15Cr-15N alloy and PNC316 stainless steel as being observed in the electron-irradiated austenitic stainless steels. We discussed the difference of the void denuded zone distribution in both steels under low and high fluencie. These results suggest that the grain boundary characteristics and its effect on void denuded zone formation will play a role for the void swelling under neutron irradiation in austenitic stainless steels.
Inoue, Toshihiko; Ogawa, Ryuichiro; Inoue, Masaki; Yoshitake, Tsunemitsu; Nishinoiri, Kenji
no journal, ,
no abstracts in English
Ishimi, Akihiro; Katsuyama, Kozo; Maeda, Koji; Nishinoiri, Kenji
no journal, ,
no abstracts in English
Ichikawa, Shoichi; Katsuyama, Kozo; Maeda, Koji; Nishinoiri, Kenji; Uwaba, Tomoyuki; Koyama, Shinichi
no journal, ,
Out of pile bundle compressive test plan for a thick pin is carried out in order to evaluate BDI behavior of "Monju" advanced reactor and demonstration reactor.
Miwa, Shuhei; Ishimi, Akihiro; Tanaka, Kosuke; Sato, Isamu; Hirosawa, Takashi; Obayashi, Hiroshi; Koyama, Shinichi; Katsuyama, Kozo; Nishinoiri, Kenji; Osaka, Masahiko; et al.
no journal, ,
The experimental studies for the evaluations of fission products migration behaviors focused on the evaluations of chemical form were planned to improve the evaluation accuracy of the source term in a severe accident of nuclear power plant.