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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.

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:75.29(Nuclear Science & Technology)

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

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:18.98(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:52.37(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:0.00(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

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

Oral presentation

Development of MCNP6 model for HTTR using the explicit random method

Ho, H. Q.; Honda, Yuki; Goto, Minoru; Takada, Shoji; Ishitsuka, Etsuo

no journal, , 

Coated fuel particles (CFPs) play an important role to the passive safety feature of the high temperature engineering test reactor (HTTR). However, random distribution of the CFPs also makes the simulation become more difficult and therefore affects the quality of the HTGR benchmark assessment. The highly accurate calculation enables the design of a commercial HTGR to operate with low cost and high performance. The purpose of this study was to develop MCNP model for the HTTR by using the explicit random model, namely Realized Random Packing (RRP), to improve the accuracy of the benchmark assessment. The RRP model was validated by comparing with the conventional uniform model as well as the experimental data. The neutronic and criticality calculations were performed by using MCNP6 code with ENDF/B-VII.1 nuclear data library.

Oral presentation

Numerical investigation of random packing for CFPs of HTTR using MCNP

Ho, H. Q.; Honda, Yuki; Goto, Minoru; Takada, Shoji

no journal, , 

18 (Records 1-18 displayed on this page)
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