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JAEA Reports

Development of once-through type densitometer

Onozawa, Atsushi; Kushida, Teruo; Kanazawa, Hiroyuki

JAERI-Tech 2004-061, 39 Pages, 2004/11

JAERI-Tech-2004-061.pdf:8.64MB

The swelling observed on irradiated fuels is caused by the accumulation of fission products and irradiation defects. The swelling ratio is changed along with radius region in the pellet due to burn up difference caused by that of neutron flux. To investigate the swelling behavior at the small area of the pellet, it is needed to measure the density of fuel fragments picked from an irradiated pellet. In this circumstance, once-through type densitometer was developed to measure the density of the small irradiated specimen precisely and to handle the samples easily with remote control systems. Several kinds of metallic and ceramic standard specimens are prepared to investigate the dependence of the sample weight, density and porosity on the accuracy. The results of characteristic examination using these specimens indicate that this densitometer has enough accuracy. In addition, some parts of this apparatus are controlled by motor drive units, which made it possible to measure the density full-automatically.

JAEA Reports

Influence of plutonium contents in MOX fuel on destructive forces at fuel failure in the NSRR experiment

Nakamura, Jinichi; Sugiyama, Tomoyuki; Nakamura, Takehiko; Kanazawa, Toru; Sasajima, Hideo

JAERI-Tech 2003-008, 32 Pages, 2003/03

JAERI-Tech-2003-008.pdf:1.49MB

no abstracts in English

Journal Articles

Estimation of spent fuel compositions from light water reactors

Ando, Yoshihira*; Nishihara, Kenji; Takano, Hideki

Journal of Nuclear Science and Technology, 37(10), p.924 - 933, 2000/10

no abstracts in English

Journal Articles

Rim structure formation of isothermally irradiated UO$$_{2}$$ fuel discs

Une, Katsumi*; Nogita, Kazuhiro*; Shiratori, Tetsuo; Hayashi, Kimio

Journal of Nuclear Materials, 288(1), p.20 - 28, 2000/09

 Times Cited Count:16 Percentile:24.03

no abstracts in English

Journal Articles

Fission gas release behavior of high burnup UO$$_{2}$$ fuel under reactivity initiated accident conditions

Sasajima, Hideo; Nakamura, Jinichi; Fuketa, Toyoshi; Uetsuka, Hiroshi

Journal of Nuclear Science and Technology, 36(11), p.1101 - 1104, 1999/11

 Times Cited Count:1 Percentile:86.08(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

A Study on density, melting point, thermal expansion, creep, thermal diffusivity and thermal conductivity of the simulated rock-like oxide (ROX) fuels

Yanagisawa, Kazuaki; Omichi, Toshihiko*; Shirasu, Noriko; Muromura, Tadasumi; *

JAERI-Tech 99-032, 65 Pages, 1999/03

JAERI-Tech-99-032.pdf:3.23MB

no abstracts in English

Journal Articles

Thermal diffusivity of high burnup UO$$_{2}$$ pellet

Nakamura, Jinichi; Uchida, Masaaki; Uetsuka, Hiroshi; Furuta, Teruo

IAEA-TECDOC-1036, 0, p.127 - 138, 1998/08

no abstracts in English

JAEA Reports

Detailed description and user's manual of high burnup fuel analysis code EXBURN-I

Suzuki, Motoe; Saito, Hioraki*

JAERI-Data/Code 97-046, 210 Pages, 1997/11

JAERI-Data-Code-97-046.pdf:5.41MB

no abstracts in English

Journal Articles

Thermal diffusivity measurement of high burnup UO$$_{2}$$ pellet

Nakamura, Jinichi; Uchida, Masaaki; Uetsuka, Hiroshi; Kodaira, Tsuneo; Yamahara, Takeshi;

Proc. of Int. Topical Meeting on LWR Fuel Performance, 0, p.499 - 506, 1997/03

no abstracts in English

Journal Articles

Modified conversion ratio measurement in light water-moderated UO$$_{2}$$ lattices

Nakajima, Ken;

Nuclear Technology, 113, p.375 - 379, 1996/03

 Times Cited Count:5 Percentile:53.16(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal diffusivity of high burnup UO$$_{2}$$ pellet irradiated at HBWR

Nakamura, Jinichi; Furuta, Teruo; Sukegawa, T

HPR-347, 12 Pages, 1996/00

no abstracts in English

Journal Articles

Post-irradiation examination of high burnup HBWR fuel rods at JAERI

Nakamura, Jinichi; Uetsuka, Hiroshi; Kono, Nobuaki; ; ; Furuta, Teruo

HPR-345 (Vol. II), 0, 13 Pages, 1995/00

no abstracts in English

Journal Articles

Fission product behavior in Triso-coated UO$$_{2}$$ fuel particles

Minato, Kazuo; Ogawa, Toru; Fukuda, Kosaku; ; ;

Journal of Nuclear Materials, 208, p.266 - 281, 1994/00

 Times Cited Count:33 Percentile:7.39

no abstracts in English

Journal Articles

A Model to predict the ultimate failure of coated fuel particles during core heatup events

Ogawa, Toru; Minato, Kazuo; Fukuda, Kosaku; ; ; Sekino, Hajime; ; Ito, Tadaharu; ;

Nuclear Technology, 96, p.314 - 322, 1991/12

 Times Cited Count:12 Percentile:22.03(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Behavior of Nb$$_{2}$$O$$_{5}$$ doped UO$$_{2}$$ fuel in reactivity initiated accident conditions

Yanagisawa, Kazuaki

Journal of Nuclear Science and Technology, 28(5), p.459 - 471, 1991/05

no abstracts in English

JAEA Reports

Study on behavior of niobia dopant UO$$_{2}$$ fuel under reactivity initiated accident conditions

Yanagisawa, Kazuaki; Mimura, Hideaki; Kimura, Yasuhiko

JAERI-M 90-164, 64 Pages, 1990/09

JAERI-M-90-164.pdf:4.96MB

no abstracts in English

JAEA Reports

Behavior of water reacter fuel rod

Yanagisawa, Kazuaki

JAERI-M 90-120, 320 Pages, 1990/08

JAERI-M-90-120.pdf:12.75MB

no abstracts in English

Journal Articles

Diffusion coefficients of fission products in the UO$$_{2}$$ kernel and pyrocarbon layer of BISO-coated fuel particles at extremely high temperatures

; Fukuda, Kosaku

Journal of Nuclear Materials, 174, p.35 - 44, 1990/00

 Times Cited Count:0 Percentile:100

no abstracts in English

Journal Articles

A Study on the behavior of pressurized hollow UO$$_{2}$$ fuel under reactivity initiated accident conditions

Yanagisawa, Kazuaki

Nucl. Eng. Des., 116, p.171 - 180, 1989/00

 Times Cited Count:4 Percentile:49.46

no abstracts in English

JAEA Reports

43 (Records 1-20 displayed on this page)