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Journal Articles

Research and development on high burnup HTGR fuels in JAEA

Ueta, Shohei; Mizuta, Naoki; Sasaki, Koei; Sakaba, Nariaki; Ohashi, Hirofumi; Yan, X.

Mechanical Engineering Journal (Internet), 7(3), p.19-00571_1 - 19-00571_12, 2020/06

JAEA has been progressing to design HTGR fuels for not only small-type practical HTGRs but also VHTR proposed in GIF which can be utilized for various purposes with high-temperature heat at 750 to 950 $$^{circ}$$C. To increase economy of these HTGRs, JAEA has been upgrading the design method for the HTGR fuel, which can maintain their integrities at the burnup of three to four times higher than that of the conventional HTTR fuel. Design principles and specifications of various concepts of the high burnup HTGR fuels designed by JAEA are reported. As the latest results on post-irradiation examinations of the high burnup HTGR fuel progressing in a framework of international collaboration with Kazakhstan, irradiation shrinkage rate of the fuel compact as a function of fast neutron fluence was obtained at around 100 GWd/t. Furthermore, the future R&Ds needed for the high burnup HTGR fuel are described based on these experimental results.

Journal Articles

Research and development on high burnup HTGR fuels in JAEA

Ueta, Shohei; Mizuta, Naoki; Sasaki, Koei; Sakaba, Nariaki; Ohashi, Hirofumi; Yan, X.

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05

JAEA has been progressing to design HTGR fuels for not only small-type practical HTGRs but also VHTR proposed in GIF which can be utilized for various purposes with high-temperature heat at 750 to 950 $$^{circ}$$C. To increase economy of these HTGRs, JAEA has been upgrading the design method for the HTGR fuel, which can maintain their integrities at the burnup of three to four times higher than that of the conventional HTTR fuel. Design principles and specifications of various concepts of the high burnup HTGR fuels designed by JAEA are reported. As the latest results on post-irradiation examinations of the high burnup HTGR fuel progressing in a framework of international collaboration with Kazakhstan, irradiation shrinkage rate of the fuel compact as a function of fast neutron fluence was obtained at around 100 GWd/thm. Furthermore, the future R&Ds needed for the high burnup HTGR fuel are described based on these experimental results.

Journal Articles

Study of SiC-matrix fuel element for HTGR

Mizuta, Naoki; Aoki, Takeshi; Ueta, Shohei; Ohashi, Hirofumi; Yan, X.

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 5 Pages, 2019/05

Enhancement of safety and cooling performance of fuel elements are desired for a commercial High Temperature Gas-cooled Reactor (HTGR). Applying sleeveless fuel elements and dual side directly cooling structures with oxidation resistant SiC-matrix fuel compact has a possibility of improving safety and cooling performance at the pin-in-block type HTGR. The irradiated effective thermal conductivity of a fuel compact is an important physical property for core thermal design of the pin-in-block type HTGR. In order to discuss the irradiated effective thermal conductivity of the SiC-matrix fuel compact which could improve the cooling performance of the reactor, the maximum fuel temperature during normal operation of the pin-in-block type HTGR with dual side directly cooling structures are analytically evaluated. From these results, the desired irradiated thermal conductivity of SiC matrix are discussed. In addition, the suitable fabrication method of SiC-matrix fuel compact is examined from viewpoints of the sintering temperature, the purity and the mass productivity.

JAEA Reports

A Conceptual study of oxidization resistant fuel compact for High Temperature Gas-cooled Reactors

Sawa, Kazuhiro; Tobita, Tsutomu*; Suzuki, Shuichi*; Yoshimuta, Shigeharu*; Oda, Takefumi*; Watarumi, Kazutoshi*

JAERI-Tech 99-077, p.41 - 0, 1999/11

JAERI-Tech-99-077.pdf:5.23MB

no abstracts in English

JAEA Reports

Development of advanced fabrication technology for high-temperature gas-cooled reactor fuel; Reduction of coating failure fraction

Minato, Kazuo; ; Tobita, Tsutomu*; Fukuda, Kosaku; Yoshimuta, Shigeharu*; *; *; *; *

JAERI-Research 98-070, 25 Pages, 1998/11

JAERI-Research-98-070.pdf:2.18MB

no abstracts in English

Journal Articles

Improvements in quality of as-manufactured fuels for high-temperature gas-cooled reactors

Minato, Kazuo; ; Tobita, Tsutomu*; Fukuda, Kosaku; *; *; *; *

Journal of Nuclear Science and Technology, 34(3), p.325 - 333, 1997/03

 Times Cited Count:16 Percentile:77.16(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Fuel temperature prediction during high burnup HTGR fuel irradiation test; US-JAERI irradiation test for HTGR fuel

Sawa, Kazuhiro; Fukuda, Kosaku; R.Acharya*

JAERI-Tech 94-038, 46 Pages, 1995/01

JAERI-Tech-94-038.pdf:1.26MB

no abstracts in English

JAEA Reports

Construction of VHTRC(Very High Temperature Reactor Critical Assembly)

; Akino, Fujiyoshi; Yamane, Tsuyoshi; ; Kitadate, Kenji; ; Takeuchi, Motoyoshi; Ono, Toshihiko; Kaneko, Yoshihiko

JAERI 1305, 138 Pages, 1987/08

JAERI-1305.pdf:5.59MB

no abstracts in English

JAEA Reports

Irradiation Experiments of Coted Particle Fuels by Gas-Swept Capsules,(II); Irradiation by 75F4A and 75F5A Capsules

; ; ; Tobita, Tsutomu; Minato, Kazuo; Yamamoto, Katsumune; ;

JAERI-M 87-020, 79 Pages, 1987/02

JAERI-M-87-020.pdf:4.96MB

no abstracts in English

Journal Articles

Diffusion of fission products in the matrix graphite for VHTR fuel compacts

; ; Ikawa, Katsuichi

Journal of Nuclear Science and Technology, 21(2), p.126 - 132, 1984/00

 Times Cited Count:7 Percentile:62.34(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Irradiation experiments of VHTR reference fuels by an in-pile gas loop(OGL-1)

; ; ; Minato, Kazuo; ; Ikawa, Katsuichi

Nihon Genshiryoku Gakkai-Shi, 26(1), p.57 - 74, 1984/00

 Times Cited Count:1 Percentile:19.62(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Irradiation Test of The 1st and 2nd OGL-1 Fuel Assemblies

Ikawa, Katsuichi; ; ; ; ; Minato, Kazuo; Iwamoto, K.; ; ;

JAERI-M 83-012, 251 Pages, 1983/03

JAERI-M-83-012.pdf:17.56MB

no abstracts in English

Journal Articles

Development of HTR fuel

Ikawa, Katsuichi

Genshiryoku Kogyo, 28(8), p.53 - 57, 1982/00

no abstracts in English

Journal Articles

Detection of failed coated particles in HTGR fuels by acid leaching

; Minato, Kazuo; Ikawa, Katsuichi; ;

Journal of Nuclear Science and Technology, 18(11), p.887 - 894, 1982/00

 Times Cited Count:4 Percentile:53.16(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Status of HTGR fuel

; ; *; Ikawa, Katsuichi

Nihon Genshiryoku Gakkai-Shi, 24(6), p.429 - 434, 1982/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Thermal Expansion of HTGR Fuel Compacts

; Iwamoto, K.; Ikawa, Katsuichi

JAERI-M 9052, 19 Pages, 1980/08

JAERI-M-9052.pdf:1.25MB

no abstracts in English

JAEA Reports

Concentration Profile of Radioactive Nuclides in Graphito Sleave of Reduced Size Fuel Rod for HTGR

; Iwamoto, K.; Ikawa, Katsuichi

JAERI-M 8952, 16 Pages, 1980/07

JAERI-M-8952.pdf:0.84MB

no abstracts in English

JAEA Reports

Comparison of Water Vapor Corrosion between Resin-Bonded and Silicon-Bonded Graphite Compacts

Ikawa, Katsuichi; Tobita, Tsutomu; Iwamoto, K.

JAERI-M 7477, 9 Pages, 1978/01

JAERI-M-7477.pdf:0.51MB

no abstracts in English

JAEA Reports

Measurement of Ruptured Coated Fuel Particles in the Fuel Compact by Acid Leach Techniques

Tobita, Tsutomu; Iwamoto, K.

JAERI-M 5265, 19 Pages, 1973/05

JAERI-M-5265.pdf:0.96MB

no abstracts in English

22 (Records 1-20 displayed on this page)