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JAEA Reports

BDI behavior evaluation of an upgraded Monju core and a demonstration core, 1; Plans for the out of pile bundle compressive tests for large diameter pins

Ichikawa, Shoichi; Haga, Hiroyuki; Katsuyama, Kozo; Uwaba, Tomoyuki; Maeda, Koji; Nishinoiri, Kenji

JAEA-Testing 2012-001, 36 Pages, 2012/07

JAEA-Testing-2012-001.pdf:11.48MB

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 ($$phi$$ 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.

JAEA Reports

Establishment of reassembly technique of capsule type irradiation rig

Ichikawa, Shoichi; Abe, Kazuyuki; Haga, Hiroyuki; Kajima, Hisashi*; Sakurai, Satoshi*; Katsuyama, Kozo; Maeda, Koji; Nishinoiri, Kenji

JAEA-Technology 2011-032, 46 Pages, 2012/01

JAEA-Technology-2011-032.pdf:8.46MB

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.

Journal Articles

Interrelationship between true stress-true strain behavior and deformation microstructure in the plastic deformation of neutron-irradiated or work-hardened austenitic stainless steel

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

JAEA Reports

Proceedings of the 25th anniversary meeting of the Alpha-Gamma facility

Kajitani, Yukio; ; Abe, Kazuyuki; Osaka, Masahiko; ; Hirosawa, Takashi; Koyama, Shinichi

PNC TN9440 97-004, 186 Pages, 1997/02

PNC-TN9440-97-004.pdf:21.19MB

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.

Journal Articles

None

; Nagamine, Tsuyoshi; ; ; Matsushima, Hideya

Donen Giho, (74), p.80 - 85, 1990/06

None

JAEA Reports

None

*; *; *; Matsushima, Hideya*

PNC TN9410 89-177, 34 Pages, 1989/02

PNC-TN9410-89-177.pdf:1.13MB

None

JAEA Reports

None

*; *; *; Matsushima, Hideya*

PNC TN9410 89-176, 27 Pages, 1989/01

PNC-TN9410-89-176.pdf:1.16MB

None

JAEA Reports

None

*; *; *

PNC TN9410 89-175, 31 Pages, 1989/01

PNC-TN9410-89-175.pdf:1.03MB

None

JAEA Reports

None

Tachi, Hirokazu; Nishinoiri, Kenji; Hirasawa, Hisao; Uruwashi, Shinichi; Hasegawa, Masahiro

PNC TN9410 88-190, 53 Pages, 1988/01

PNC-TN9410-88-190.pdf:3.03MB

None

JAEA Reports

None

*; *; *

PNC TN9410 87-205, 26 Pages, 1987/10

PNC-TN9410-87-205.pdf:3.22MB

None

JAEA Reports

None

*; *; *

PNC TN9410 87-192, 20 Pages, 1987/02

PNC-TN9410-87-192.pdf:1.31MB

None

JAEA Reports

None

*; *; *

PNC TN9410 86-146, 52 Pages, 1986/05

PNC-TN9410-86-146.pdf:6.9MB

None

JAEA Reports

None

*; *; *

PNC TN9410 85-145, 51 Pages, 1985/11

PNC-TN9410-85-145.pdf:7.62MB

None

JAEA Reports

Postirradiation examination of "JOYO" MK-II structural materials irradiation rig (Fab. No. PRS040); Nondestructive testing on irradiation rig and its compartments

*; *; *; *

PNC TN9410 85-133, 64 Pages, 1985/02

PNC-TN9410-85-133.pdf:8.98MB

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 $$times$$ 10$$^{21}$$n/cm$$^{2}$$ (E$$geqq$$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.

Journal Articles

None

; Usui, Keiji; ;

International Topical Meeting on Nuclear and Hazardous Waste Management (SPECTRUM '94), , 

None

Oral presentation

The Evaluation of strength properties of irradiated PNC316 cladding tube

Inoue, Toshihiko; Ogawa, Ryuichiro; Akasaka, Naoaki; Nishinoiri, Kenji

no journal, , 

no abstracts in English

Oral presentation

Irradiation effect on microstructure of modified SUS316 stainless steel cladding irradiated at elevated temperature to high dose

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 Fe$$_{2}$$P 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.

Oral presentation

Transient burst techniques and results of the examination for irradiated PNC316 steel

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.

Oral presentation

Effect of fine precipitate on swelling behavior of heavily-irradiated PNC316 stainless steel

Yamashita, Shinichiro; Sekine, Manabu*; Tachi, Yoshiaki; Akasaka, Naoaki; Nishinoiri, Kenji; Takahashi, Heishichiro

no journal, , 

no abstracts in English

Oral presentation

The Evaluation of tensile strength properties of irradiated PNC1520 cladding tube

Inoue, Toshihiko; Ogawa, Ryuichiro; Akasaka, Naoaki; Nishinoiri, Kenji

no journal, , 

no abstracts in English

31 (Records 1-20 displayed on this page)