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Journal Articles

Influences of the ZrC coating process and heat treatment on ZrC-coated kernels used as fuel in Pu-burner high temperature gas-cooled reactor in Japan

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:0.01(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$$_{2}$$-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$$_{2}$$-YSZ kernel simulating PuO$$_{2}$$-YSZ kernel. We found both Zr-rich grains and Ce-rich grains to be densely distributed in that region including surface of CeO$$_{2}$$-YSZ kernel. On the other hand, it has been reported that there was a porous region near surface of the CeO$$_{2}$$-YSZ kernel of Batch I. This finding confirms that Ce-rich grains near surface of CeO$$_{2}$$-YSZ kernels coated with ZrC layers have been corroded during the deposition of the ZrC layer, whereas the Zr-rich grains were hardly affected.

Journal Articles

Study on plutonium burner high temperature gas-cooled reactor in Japan; Introduction scenario, reactor safety and fabrication tests of the 3S-TRISO fuel

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:39.17(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$$_{2}$$) 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.

JAEA Reports

Code-B-2.5.2 for stress calculation for SiC-TRISO fuel particle

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$$_{2}$$ (PuO$$_{2}$$-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.

Journal Articles

Microstructures of ZrC coated kernels for fuel of Pu-burner high temperature gas-cooled reactor in Japan

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:2 Percentile:42.44(Materials Science, Multidisciplinary)

In order to realize Pu-burner high temperature gas-cooled reactor (HTGR), coated fuel particles (CFPs) with PuO$$_{2}$$-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$$_{2}$$-YSZ kernels (CeO$$_{2}$$-YSZ particles or commercially available YSZ particles). Ce was used as simulating element of Pu. In this manuscript, microstructures of ZrC coated CeO$$_{2}$$-YSZ or YSZ particles were reported.

Journal Articles

Tritium accounting stability of a ZrCo bed with "In-bed" gas flowing calorimetry

Hayashi, Takumi; Suzuki, Takumi; Yamada, Masayuki; Nishi, Masataka

Fusion Science and Technology, 48(1), p.317 - 323, 2005/07

 Times Cited Count:10 Percentile:59.05(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Chlorination of UO$$_{2}$$, PuO$$_{2}$$ and rare earth oxides using ZrCl$$_{4}$$ in LiCl-KCl eutectic melt

Sakamura, Yoshiharu*; Inoue, Tadashi*; Iwai, Takashi; Moriyama, Hirotake*

Journal of Nuclear Materials, 340(1), p.39 - 51, 2005/04

 Times Cited Count:26 Percentile:84.93(Materials Science, Multidisciplinary)

A new chlorination method using ZrCl$$_{4}$$ in a molten salt has been investigated for the pyrometallurgical reprocessing of spent oxide fuels. UO$$_{2}$$, PuO$$_{2}$$ and rare earth oxides(La$$_{2}$$O$$_{3}$$, CeO$$_{2}$$, Nd$$_{2}$$O$$_{3}$$ and Y$$_{2}$$O$$_{3}$$) were allowed to react with ZrCl$$_{4}$$ in a LiCl-KCl eutectic salt at 500$$^{circ}$$C to give a metal chloride solution and a precipitate of ZrO$$_{2}$$. By keeping the system quite still, the solution settled so that the ZrO$$_{2}$$ precipitate could be separated.

JAEA Reports

Research and development plan for advanced high temperature gas cooled reactor fuels and graphite components (Contract research)

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.

Journal Articles

Research and development on HTGR fuel in the HTTR project

Sawa, Kazuhiro; Ueta, Shohei

Nuclear Engineering and Design, 233(1-3), p.163 - 172, 2004/10

 Times Cited Count:47 Percentile:94.14(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.

Journal Articles

Coated particle fuel for high-temperature gas-cooled reactors

Minato, Kazuo

Seramikkusu, 39(10), p.830 - 833, 2004/10

no abstracts in English

Journal Articles

The High temperature gas cooled reactor fuel

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 2200$$^{circ}$$C. 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.

Journal Articles

Advanced coated particle fuels; Experience of ZrC-triso fuel development and beyond

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

Journal Articles

Research and development of ZrC-coated particle fuel

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$$_{2}$$ 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.

JAEA Reports

Plan to development of ZrC-TRISO coated fuel particle and construction of ZrC coater

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

Journal Articles

Structure and electrical transport property of a silicopnictide ZrCuSiP

Abe, Hideki*; Yoshii, Kenji

Journal of Solid State Chemistry, 165(2), p.372 - 374, 2002/05

 Times Cited Count:8 Percentile:30.96(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Reversible disproportionation of ZrCo under high temperature and hydrogen pressure

Konishi, Satoshi; Nagasaki, Takanori; Okuno, Kenji

Journal of Nuclear Materials, 223, p.294 - 299, 1995/00

 Times Cited Count:82 Percentile:98.76(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Equilibrium hydrogen pressure on the solid solutions of ZrCo-HfCo intermetallic compounds

Konishi, Satoshi; Nagasaki, Takanori; Hayashi, Takumi; Okuno, Kenji

Journal of Nuclear Materials, 223, p.300 - 304, 1995/00

 Times Cited Count:21 Percentile:87.03(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Improvements in ZrCo based tritium storage media

Konishi, Satoshi; Nagasaki, Takanori; Hayashi, Takumi; Okuno, Kenji

Fusion Technology, 26(3), p.668 - 672, 1994/11

no abstracts in English

Journal Articles

Early experiments of JAERI fuel cleanup system at the tritium systems test assembly

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:3 Percentile:41.62(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Quick analysis of free carbon in metal carbide by plasma oxidation

Ogawa, Toru; Fukuda, Kosaku

Journal of the American Ceramic Society, 73(8), p.2558 - 2560, 1990/08

 Times Cited Count:3 Percentile:26.92(Materials Science, Ceramics)

no abstracts in English

Journal Articles

The Oxidation behavior of ZrC coating and powder studied by laser Raman spectroscopy and X-ray diffraction

; Ogawa, Toru; Fukuda, Kosaku

Journal of Nuclear Materials, 175, p.266 - 269, 1990/00

 Times Cited Count:14 Percentile:88.65(Materials Science, Multidisciplinary)

no abstracts in English

38 (Records 1-20 displayed on this page)