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Journal Articles

Fuel performance under continuous high-temperature operation of the HTTR

Ueta, Shohei; Aihara, Jun; Sakaba, Nariaki; Honda, Masaki*; Furihata, Noboru*; Sawa, Kazuhiro

Journal of Nuclear Science and Technology, 51(11-12), p.1345 - 1354, 2014/11

 Times Cited Count:4 Percentile:36.81(Nuclear Science & Technology)

Although the HTTR fuel was the first mass-produced HTGR fuel in Japan, it has been fabricated with the highest quality in the world on the basis of design principle and safety criteria to minimize both as-fabricated failure and on-operating-additional failure of the coated fuel particle. A precise technology for evaluating irradiation performance of the HTTR fuel has been developed by measuring fission gases released from fuel and constructing the fission gas release model. Through the HTTR operations including the continuous high temperature operation with 950 $$^{circ}$$C and 50 days, the measured fractional release of fission gas from fuel resulted less than 1.2 $$times$$ 10$$^{-8}$$, and a superior irradiation performance of Japanese HTGR fuel has been demonstrated. The HTTR fuel technologies could make a prospect for realization of the practical HTGR as well as the VHTR as a Generation IV nuclear power plant before the rest of the world.

Journal Articles

Development of high temperature gas-cooled reactor (HTGR) fuel in Japan

Ueta, Shohei; Aihara, Jun; Sawa, Kazuhiro; Yasuda, Atsushi*; Honda, Masaki*; Furihata, Noboru*

Progress in Nuclear Energy, 53(7), p.788 - 793, 2011/09

 Times Cited Count:21 Percentile:86.19(Nuclear Science & Technology)

In Japan, high temperature gas-cooled reactor (HTGR) fuel fabrication technologies have been developed by Nuclear Fuel Industries, Ltd. (NFI) with the collaboration of JAEA through the HTTR project since 1960's. NFI successfully fabricated first and second loading fuel (0.9 tU each) for the HTTR of JAEA. Its excellent quality was confirmed from the first loading fuel through the long-termed high temperature operation by the end of March 2010. Based on the HTTR fuel technologies, silicon carbide (SiC) coated fuel is being developed for burn-up extension. For an advanced fuel designs, replacement of the SiC layer by a zirconium carbide (ZrC) layer is a very promising example. JAEA has performed ZrC coating tests to investigate the influence of coating parameters and material properties such as stoichiometry and density of ZrC.

Journal Articles

Development of high temperature gas-cooled reactor fuel for extended burnup

Ueta, Shohei; Aihara, Jun; Honda, Masaki*; Furihata, Noboru*; Sawa, Kazuhiro

Proceedings of 18th International Conference on Nuclear Engineering (ICONE-18) (CD-ROM), 2 Pages, 2010/05

Very High Temperature Reactor (VHTR) fuel is required to have excellent safety performance up to burnups of about 15 to 20% fissions per initial metal atom (FIMA), how are higher than the design of the Japanese HTTR fuel, 3.6% FIMA. In order to keep the integrity of TRISO fuel against the internal pressure increasing according to burnup, the SiC and the buffer layers should be designed to be thick, enough to increase the mechanical strength and to moderate the internal pressure in TRISO fuel, respectively. So far JAEA developed so-called extended burnup fuels whose target burnup was higher than those of the HTTR, and confirmed their performance by irradiation tests up to 9% FIMA. In this R&D, the new TRISO fuel designed for further extended burnup were fabricated. Indicated by the sphericity of the particle and so on, the quality of the new fuel resulted better than the past fuel for extended burnup.

Oral presentation

Conceptual design of small-sized high temperature gas-cooled reactor system for electricity generation and district heating

Kasuga, Shoji*; Kubota, Kenichi*; Okamoto, Futoshi*; Maekawa, Isamu*; Furihata, Noboru*; Saito, Masanao*; Kido, Yuji*; Ohashi, Hirofumi; Tachibana, Yukio; Kunitomi, Kazuhiko

no journal, , 

Conceptual design of a small-sized HTGR for electricity generation and district heating has been conducted by JAEA with support of Japanese vendors: Toshiba Corporation, Fuji Electric, Kawasaki Heavy Industries, Nuclear Fuel Industries, Shimizu Corporation, and Marubeni Utility Services. System design as well as nuclear design of the first core of HTR50S using the same CFPs as the HTTR has been performed and the nuclear design shows upgraded performance of the reactor compared with the HTTR.

Oral presentation

Conceptual design study of small-sized high temperature gas-cooled reactor for developing countries, 1; Overviews

Tachibana, Yukio; Ohashi, Hirofumi; Sato, Hiroyuki; Suzuki, Tetsu*; Ohashi, Kazutaka*; Mori, Yuichiro*; Furihata, Noboru*

no journal, , 

no abstracts in English

Oral presentation

Conceptual design study of small-sized high temperature gas-cooled reactor for developing countries, 3; Fuel design

Ueta, Shohei; Aihara, Jun; Mizutani, Yoshitaka; Ohashi, Hirofumi; Sakaba, Nariaki; Tachibana, Yukio; Honda, Masaki*; Tanaka, Hideki*; Furihata, Noboru*

no journal, , 

In the small-sized high temperature gas-cooled reactor, the improved fuel of which the burnup is designed over 100 GWd/t is used in order to upgrade economy and to decrease radioactive waste. On the other hand, to attain over three times higher burnup than that of a conventional HTTR fuel, 33 GWd/t, researches and developments of the fuel should be needed with regards to the design preventing the fuel from the failure by internal pressure due to gases in the coated fuel particle, the technologies for fabrication of the improved fuel, and the irradiation test to confirm its integrity under the irradiation. A design work, fabrication tests and a plan of the irradiation test for the improved fuel in order to demonstrate the performance are reported.

Oral presentation

Collaboration with Republic of Kazakhstan regarding development of HTGR, 2; Collaboration of irradiation performance of HTGR fuel

Ueta, Shohei; Mizutani, Yoshitaka; Sakaba, Nariaki; Furihata, Noboru*; Honda, Masaki*; Asset, S.*; Gizatulin, S.*; Chakrov, P.*

no journal, , 

A capsule irradiation test with the high temperature gas-cooled reactor (HTGR) fuel by WWR-K in the Institute of Nuclear Physics of the Republic of Kazakhstan (INP) is being carried out. The HTGR fuel specimens were newly designed at the target burnup of 100 GWd/t. A plan of the irradiation test and results on evaluation of the integrity of the HTGR fuel specimen based on fission gas (FP) release rate under the irradiation are reported.

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