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Search Results: Records 1-9 displayed on this page of 9
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Journal Articles

Decrease of cesium release from irradiated UO$$_{2}$$ fuel in helium atmosphere under elevated pressure of 1.0MPa at temperature up to 2,773K

Hidaka, Akihide; Kudo, Tamotsu; Nakamura, Takehiko; Uetsuka, Hiroshi

Journal of Nuclear Science and Technology, 39(7), p.759 - 770, 2002/07

https://doi.org/10.3327/jnst.39.759
 Times Cited Count：6 Percentile：39.48(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of advanced neutron radiography for inspection on irradiated fuels and materials, 3; Examination of neutron imaging plate and computed tomography methods on unirradiated fuel rod

Yasuda, Ryo; Matsubayashi, Masahito; Nakata, Masahito; Harada, Katsuya; Amano, Hidetoshi; Ando, Hitoshi*; Sasajima, Fumio; Nishi, Masahiro; Horiguchi, Yoji

JAERI-Tech 2002-001, 23 Pages, 2002/02

JAERI-Tech-2002-001.pdf:3.79MB

Advanced neutron radiography techniques such as neutron imaging plate (NIP) and Computed Tomography (CT) methods have been investigated the practicality for Post Irradiation Examination (PIE). In this work, an unirradiated fuel rod was examined by NIP and CT methods in order to collect the fundamental data for applying these techniques to PIE.The fuel rod is composed of seven-enriched UO2 pellet and two-natural UO2 pellet that are loaded into a Zircaloy tube. There are somewhat difference in the size and shape among those UO2 pellets. A transmitted and cross-sectional images were obtained by NIP and CT methods, respectively.In the NIP image, the difference in the size, shape, and enrichment among the UO2 pellets is obviously recognized. In the case of CT method, the images clearly show the detailed shape of the cross section in the pellets, in addition, the difference in the enrichment between the natural and enriched pellets is recognized.

Journal Articles

MOX fuel behavior under reactivity accident conditions

Sasajima, Hideo; Fuketa, Toyoshi; Ishijima, Kiyomi; Kikuchi, Keiichi*; Abe, Tomoyuki*

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

JAEA Reports

Measurements and calculations of neutron interaction effects of a two-coupled system in water

Miyoshi, Yoshinori; Suzaki, Takenori; ; Kobayashi, Iwao

JAERI-M 90-112, 45 Pages, 1990/07

JAERI-M-90-112.pdf:0.88MB

no abstracts in English

Journal Articles

Metallic phases precipitated in UO$$_{2}$$ fuel,I; Phases in simulated fuel

Muromura, Tadasumi; Adachi, Takeo; Takeishi, Hideyo; Yoshida, Zenko; ;

Journal of Nuclear Materials, 151, p.318 - 326, 1988/00

https://doi.org/10.1016/0022-3115(88)90026-8

no abstracts in English

Journal Articles

Metallic phases precipitated in UO$$_{2}$$ fuel, 2; Insoluble residue in simulated fuel

Adachi, Takeo; Muromura, Tadasumi; Takeishi, Hideyo;

Journal of Nuclear Materials, 160, p.81 - 87, 1988/00

https://doi.org/10.1016/0022-3115(88)90011-6
 Times Cited Count：21 Percentile：85.61(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

KENO-IV Code Benchmark Calculation,9; Three Clusters of UO$$_{2}$$ Rods Lattice

; ; Shimooke, Takanori; *

JAERI-M 9168, 34 Pages, 1980/11

JAERI-M-9168.pdf:2.21MB

no abstracts in English

JAEA Reports

Experiments and Calculations on $$beta$$$$_{e}$$$$_{f}$$$$_{f}$$/l for the Two Regional Cores of Light Water Moderated UO$$_{2}$$ and PuO$$_{2}$$-UO$$_{2}$$ Lattices

; *

JAERI-M 4696, 56 Pages, 1972/02

JAERI-M-4696.pdf:1.64MB

no abstracts in English

Journal Articles

Present status of nuclear fuel engineering;

Nihon Genshiryoku Gakkai-Shi, 9(9), p.555 - 558, 1967/00

no abstracts in English

9 (Records 1-9 displayed on this page)
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