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Aihara, Jun; Ueta, Shohei; Honda, Masaki*; Mizuta, Naoki; Goto, Minoru; Tachibana, Yukio; Okamoto, Koji*
Journal of Nuclear Science and Technology, 58(1), p.107 - 116, 2021/01
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)The concept of a Pu-burner high temperature gas-cooled reactor (HTGR) has been proposed for purpose of more safely reducing amount of recovered Pu. This concept employs coated fuel particles (CFPs) with ZrC coated PuO
-YSZ kernel and with tristructural (TRISO) coating for very high Pu burn-up and high nuclear proliferation resistance. In this report, we investigate the microstructure of the region that includes the surface of an as-fabricated CeO-YSZ kernel simulating PuO-YSZ kernel. We found both Zr-rich grains and Ce-rich grains to be densely distributed in that region including surface of CeO-YSZ kernel. On the other hand, it has been reported that there was a porous region near surface of the CeO-YSZ kernel of Batch I. This finding confirms that Ce-rich grains near surface of CeO-YSZ kernels coated with ZrC layers have been corroded during the deposition of the ZrC layer, whereas the Zr-rich grains were hardly affected.
Ueta, Shohei; Mizuta, Naoki; Fukaya, Yuji; Goto, Minoru; Tachibana, Yukio; Honda, Masaki*; Saiki, Yohei*; Takahashi, Masashi*; Ohira, Koichi*; Nakano, Masaaki*; et al.
Nuclear Engineering and Design, 357, p.110419_1 - 110419_10, 2020/02
Times Cited Count：1 Percentile：10.11(Nuclear Science & Technology)The concept of a plutonium (Pu) burner HTGR is proposed to incarnate highly-effective Pu utilization by its inherent safety features. The security and safety fuel (3S-TRISO fuel) employs the coated fuel particle with a fuel kernel made of plutonium dioxide (PuO) and yttria stabilized zirconia (YSZ) as an inert matrix. This paper presents feasibility study of Pu burner HTGR and R&D on the 3S-TRISO fuel.
Aihara, Jun; Goto, Minoru; Ueta, Shohei; Tachibana, Yukio
JAEA-Data/Code 2019-018, 22 Pages, 2020/01
JAEA-Data-Code-2019-018.pdf:1.39MB
Concept of Pu-burner high temperature gas-cooled reactor (HTGR) was proposed for purpose of more safely reducing amount of recovered Pu. In Pu-burner HTGR concept, coated fuel particle (CFP), with ZrC coated yttria stabilized zirconia (YSZ) containing PuO (PuO-YSZ) small particle and with tri-structural isotropic (TRISO) coating, is employed for very high burn-up and high nuclear proliferation resistance. ZrC layer is oxygen getter. On the other hand, we have developed Code-B-2.5.2 for prediction of pressure vessel failure probabilities of SiC-tri-isotropic (TRISO) coated fuel particles for HTGRs under operation by modification of an existing code, Code-B-2. The main purpose of modification is preparation of applying code for CFPs of Pu-burner HTGR. In this report, basic formulae are described.
Aihara, Jun; Ueta, Shohei; Honda, Masaki*; Mizuta, Naoki; Goto, Minoru; Tachibana, Yukio; Okamoto, Koji*
Journal of Nuclear Materials, 522, p.32 - 40, 2019/08
Times Cited Count：3 Percentile：28.63(Materials Science, Multidisciplinary)In order to realize Pu-burner high temperature gas-cooled reactor (HTGR), coated fuel particles (CFPs) with PuO-yittria stabilized zirconia (YSZ) fuel kernel coated with ZrC is employed for high nuclear proliferation resistance and very high burn-up. Japan Atomic Energy Agency (JAEA) have carried out ZrC coatings of particles which simulated PuO-YSZ kernels (CeO-YSZ particles or commercially available YSZ particles). Ce was used as simulating element of Pu. In this manuscript, microstructures of ZrC coated CeO-YSZ or YSZ particles were reported.
Hayashi, Takumi; Suzuki, Takumi; Yamada, Masayuki; Nishi, Masataka
Fusion Science and Technology, 48(1), p.317 - 323, 2005/07
Times Cited Count：10 Percentile：56.15(Nuclear Science & Technology)no abstracts in English
, PuO and rare earth oxides using ZrCl
in LiCl-KCl eutectic meltSakamura, Yoshiharu*; Inoue, Tadashi*; Iwai, Takashi; Moriyama, Hirotake*
Journal of Nuclear Materials, 340(1), p.39 - 51, 2005/04
Times Cited Count：44 Percentile：91.89(Materials Science, Multidisciplinary)A new chlorination method using ZrCl in a molten salt has been investigated for the pyrometallurgical reprocessing of spent oxide fuels. UO, PuO and rare earth oxides(LaO
, CeO, NdO and YO) were allowed to react with ZrCl in a LiCl-KCl eutectic salt at 500
C to give a metal chloride solution and a precipitate of ZrO. By keeping the system quite still, the solution settled so that the ZrO precipitate could be separated.
Sawa, Kazuhiro; Ueta, Shohei; Shibata, Taiju; Sumita, Junya; Ohashi, Jumpei; Tochio, Daisuke
JAERI-Tech 2005-024, 34 Pages, 2005/03
JAERI-Tech-2005-024.pdf:2.15MB
The Very-High-Temperature Reactor (VHTR) is one of the strong candidates for the Generation IV Nuclear Energy System. JAERI has developed Zirconium carbide (ZrC)-coated fuel particle and ZrC coating layer is expected to maintain its intactness under higher temperature and burn-up comparing conventional SiC-coating layer. JAERI carries out (1) ZrC-coating process development by large-scale coater, (2) inspection method development and (3) irradiation test and post irradiation experiment of ZrC coated particles. Also, JAERI carries out reactivity insertion tests to clarify the coating failure mechanism and tries to increase allowable temperature limit in case of reactivity insertion accident. Furthermore, JAERI develops non-destructive evaluation methods for mechanical properties of graphite components by ultrasonic testing and micro-indentation technique. This report describes these research and development plan and results of FY 2004 as a MEXT contact research.
Sawa, Kazuhiro; Ueta, Shohei
Nuclear Engineering and Design, 233(1-3), p.163 - 172, 2004/10
Times Cited Count：60 Percentile：95.36(Nuclear Science & Technology)In the high temperature gas-cooled reactors (HTGRs), refractory coated fuel particles are employed as fuel to permit high outlet coolant temperature. The High Temperature Engineering Test Reactor (HTTR) employs Tri-isotropic (Triso) coated fuel particles in the prismatic fuel assembly. Research and development on the HTTR fuel has been carried out spread over about 30 years, in fuel fabrication technologies, fuel performance, and so on. Furthermore, for upgrading of HTGR technologies, an extended burnup TRISO-coated fuel particle and an advanced type of coated fuel particle, ZrC-coated fuel particle in order to keep the integrity at higher operating temperatures has been developed. The present paper provides experiences and current status of research and development works for the HTGR fuel in the HTTR Project.
Minato, Kazuo
Seramikkusu, 39(10), p.830 - 833, 2004/10
no abstracts in English
Sawa, Kazuhiro; Ueta, Shohei; Iyoku, Tatsuo
Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 10 Pages, 2003/09
This paper provides present status of research and development for the coated fuel particle (CFPs) including the advanced ZrC-CFP. Current HTGR employs so-called TRISO-CFPs with SiC layer. In safety design of the HTGR fuels, it is important to retain fission products within CFPs so that their release to primary coolant does not exceed an acceptable level. The behavior of TRISO-CFPs has been investigated through experiments and reactor operation. These data show excellent performance of the TRISO-CFPs when they are correctly fabricated. On the other hand, the crystalline material comprising the SiC layer has a tendency to decompose at high temperature. The transition temperatures of beta-SiC (as-deposited) to alpha-SiC vary from 1600 to 2200C. ZrC is one of the transition metal carbides which are characterized by the high melting point and the thermodynamic stability etc. The CFPs with CVD-ZrC coatings have been investigated including the fabrication processes and characterization techniques developments.
Ogawa, Toru; Minato, Kazuo; Sawa, Kazuhiro
Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 6 Pages, 2003/04
no abstracts in English
Minato, Kazuo; Ogawa, Toru
Proceedings of GLOBAL2003 Atoms for Prosperity; Updating Eisenhower's Global Vision for Nuclear Energy (CD-ROM), p.1068 - 1074, 2003/00
The research and development of the ZrC-Triso coated particle fuel was reviewed, especially on the fabrication, chemical reactions, high-temperature stability, and retention of fission products. The fabrication process of stoichiometric ZrC coating layer has been established based on the in-situ generation of zirconium halide vapor. The irradiation experiments, the postirradiation heating tests, and the out-of-reactor experiments demonstrated that the ZrC coating layer is less susceptible than the SiC coating layer to chemical attack by the fission product palladium, and that the ZrC-Triso coated UO particles perform better than the normal Triso-coated particles at high temperatures, especially above 1873 K. It was revealed that the ZrC-Triso coated particles retain the fission products better than the SiC-Triso coated particles, though the ZrC coating layer is a less effective barrier to ruthenium than the SiC coating layer.
Ueta, Shohei; Tobita, Tsutomu*; Ino, Hiroichi*; Takahashi, Masashi*; Sawa, Kazuhiro
JAERI-Tech 2002-085, 41 Pages, 2002/11
JAERI-Tech-2002-085.pdf:2.66MB
no abstracts in English
Abe, Hideki*; Yoshii, Kenji
Journal of Solid State Chemistry, 165(2), p.372 - 374, 2002/05
Times Cited Count：8 Percentile：29.51(Chemistry, Inorganic & Nuclear)no abstracts in English
Konishi, Satoshi; Nagasaki, Takanori; Hayashi, Takumi; Okuno, Kenji
Journal of Nuclear Materials, 223, p.300 - 304, 1995/00
Times Cited Count：22 Percentile：86.85(Materials Science, Multidisciplinary)no abstracts in English
Konishi, Satoshi; Nagasaki, Takanori; Okuno, Kenji
Journal of Nuclear Materials, 223, p.294 - 299, 1995/00
Times Cited Count：104 Percentile：99.10(Materials Science, Multidisciplinary)no abstracts in English
Konishi, Satoshi; Nagasaki, Takanori; Hayashi, Takumi; Okuno, Kenji
Fusion Technology, 26(3), p.668 - 672, 1994/11
no abstracts in English
Konishi, Hiroyuki; Inoue, Masahiko*; Hayashi, Takumi; Ohira, Shigeru; Watanabe, Tetsuo*; Okuno, Kenji; Naruse, Yuji; Barnes, J. W.*; Bartlit, J. R.*; Anderson, J. L.*
Fusion Engineering and Design, 18, p.33 - 37, 1991/00
Times Cited Count：4 Percentile：47.68(Nuclear Science & Technology)no abstracts in English
Ogawa, Toru; Fukuda, Kosaku
Journal of the American Ceramic Society, 73(8), p.2558 - 2560, 1990/08
Times Cited Count：3 Percentile：24.36(Materials Science, Ceramics)no abstracts in English
; Ogawa, Toru; Fukuda, Kosaku
Journal of Nuclear Materials, 175, p.266 - 269, 1990/00
Times Cited Count：15 Percentile：87.94(Materials Science, Multidisciplinary)no abstracts in English
