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Journal Articles

Development of fabrication technology for oxidation-resistant fuel elements for high-temperature gas-cooled reactors

Aihara, Jun; Honda, Masaki*; Ueta, Shohei; Ogawa, Hiroaki; Ohira, Koichi*; Tachibana, Yukio

Nihon Genshiryoku Gakkai Wabun Rombunshi, 18(1), p.29 - 36, 2019/03

Japan Atomic Energy Agency carried out development of fabrication technology of oxidation resistant fuel element for improvement of safety of high temperature gas-cooled reactors in serious oxidation accident, based on precursor research in former JAEA. Dummy coated fuel particles (alumina particles) were over-coated with mixed powder of Si, C and small amount of resin to form over-coated particles, and over-coated particles were molded and hot-pressed to sinter dummy oxidation resistant fuel elements with SiC/C mixed matrix. We fabricated dummy oxidation resistant fuel elements with matrix whose Si/C mole ratio (about 0.551) is three times as large as that in precursor research. Si peak was not detected by X-ray diffraction of matrix. Better oxidation resistant was confirmed with oxidation test in 20% O$$_{2}$$ at 1673 K than that of ordinal fuel compact with ordinal graphite/carbon matrix. All dummy coated fuel particles were held in specimen after 10 h oxidation.

Journal Articles

CT injection experiment in JFT-2M

Ogawa, Hiroaki; Ogawa, Toshihide; Tsuzuki, Kazuhiro; Kawashima, Hisato; Kasai, Satoshi*; Kashiwa, Yoshitoshi; Hasegawa, Koichi; Suzuki, Sadaaki; Shibata, Takatoshi; Miura, Yukitoshi; et al.

Fusion Science and Technology, 49(2), p.209 - 224, 2006/02

 Times Cited Count:3 Percentile:24.08(Nuclear Science & Technology)

no abstracts in English

Journal Articles

High performance tokamak experiments with a ferritic steel wall on JFT-2M

Tsuzuki, Kazuhiro; Kimura, Haruyuki; Kawashima, Hisato; Sato, Masayasu; Kamiya, Kensaku; Shinohara, Koji; Ogawa, Hiroaki; Hoshino, Katsumichi; Bakhtiari, M.; Kasai, Satoshi; et al.

Nuclear Fusion, 43(10), p.1288 - 1293, 2003/10

 Times Cited Count:39 Percentile:74(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Study on decay heat removal of compact ITER

Tsuru, Daigo; Neyatani, Yuzuru; Araki, Takao*; Nomoto, Kazuhiro*; Ohira, Shigeru; Maruo, Takeshi; Hashimoto, Masayoshi*; Hada, Kazuhiko; Tada, Eisuke

Fusion Engineering and Design, 58-59, p.985 - 989, 2001/11

 Times Cited Count:4 Percentile:33.39(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Behavior of compact toroid injected into an external magnetic field

Nagata, M.*; Fukumoto, Naoyuki*; Ogawa, Hiroaki; Ogawa, Toshihide; Uehara, Kazuya; Niimi, Hironobu*; Shibata, Takatoshi; Suzuki, Yoshio; Miura, Yukitoshi; Kayukawa, Naoyuki*; et al.

Nuclear Fusion, 41(11), p.1687 - 1694, 2001/11

 Times Cited Count:12 Percentile:38.17(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Compact toroid injection as fueling in the JFT-2M tokamak

Ogawa, Toshihide; Ogawa, Hiroaki; Miura, Yukitoshi; Niimi, Hironobu*; Kimura, Haruyuki; Kashiwa, Yoshitoshi; Shibata, Takatoshi; Yamamoto, Masahiro; Fukumoto, Naoyuki*; Nagata, Masayoshi*; et al.

Journal of Nuclear Materials, 290-293, p.454 - 458, 2001/03

 Times Cited Count:7 Percentile:48.66(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Conceptual design description of a CT fueler for JT-60U

Raman, R.*; Itami, Kiyoshi

Purazuma, Kaku Yugo Gakkai-Shi, 76(10), p.1079 - 1087, 2000/10

no abstracts in English

JAEA Reports

A Design study of high electric power for fast reactor cooled by super critical light water

Koshizuka, Seiichi*

JNC TJ9400 2000-011, 102 Pages, 2000/03

JNC-TJ9400-2000-011.pdf:2.71MB

In order to evaluate the possibility to achieve high electric power by a fast reactor with supercritical light water, the design study was carried out on a large fast reactor core with high coolant outlet temperature (SCFR-H). Since the reactor coolant circuit uses once-through direct cycle where all feedwater flows through the core to the turbine at supercritical pressure, it is possible to design much simpler and more compact reactor systems and to achieve higher thermal efficiency than those of current light water reactors. The once-through direct cycle system is employed in current fossil-fired power plants. In the present study, three types of core were designed. The first is SCFR-H with blankets cooled by ascending flow, the second is SCFR-H with blankets cooled by descending flow and the third is SCFR-H with high thermal power. Every core was designed to achieve the thermal efficiency over 43%, positive coolant density reactivity coefficient and electric power over 1600MW. Core characteristics of SCFR-Hs were compared with those of SCLWR-H (electric power: 1212MW), which is a thermal neutron spectrum reactor cooled and moderated by supercritical light water, with the same diameter of the reactor pressure vessel. It was shown that SCFR-H could increase the electric power about l.7 times maximally. From the standpoint of the increase of a reactor thermal power, a fast reactor has advantages as compared with a thermal neutron reactor, because it can increase the power density by adopting tight fuel lattices and eliminating the moderator region. Thus, it was concluded that a reactor cooled by supercritical light water could further improve the cost competitiveness by using a fast neutron spectrum and achieving a higher thermal power.

Journal Articles

Tree-dimensional dynamics of a compact torus injected into magnetized plasmas II

Suzuki, Yoshio; Hayashi, Takaya*; Miyoshi, Takahiro; Kishimoto, Yasuaki; NEXT Group

Purazuma, Kaku Yugo Gakkai-Shi, 76(3), p.288 - 294, 2000/03

no abstracts in English

Journal Articles

Numerical prediction of two-phase flow behavior in a fusion reactor at an ingress-of-coolant event

Ose, Yasuo*; Takase, Kazuyuki; Akimoto, Hajime

Nihon Kikai Gakkai 2000-Nendo Nenji Taikai Koen Rombunshu, 1, p.609 - 610, 2000/00

no abstracts in English

Journal Articles

Plasma control in magnetic confinement devices; Plasma control in tokamaks

Fukuda, Takeshi

Purazuma, Kaku Yugo Gakkai-Shi, 75(12), p.1377 - 1395, 1999/12

no abstracts in English

Journal Articles

Compact toroid injection experiment in JFT-2M

Ogawa, Toshihide; Fukumoto, Naoyuki*; Nagata, Masayoshi*; Ogawa, Hiroaki; Maeno, Masaki; Hasegawa, Koichi; Shibata, Takatoshi; Uyama, Tadao*; Miyazawa, Junichi*; Kasai, Satoshi; et al.

Nuclear Fusion, 39(11Y), p.1911 - 1915, 1999/11

 Times Cited Count:32 Percentile:69.15(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Report on JFT-2M Research Collaboration Meeting

Kimura, Haruyuki

Purazuma, Kaku Yugo Gakkai-Shi, 75(6), p.758 - 759, 1999/06

no abstracts in English

Journal Articles

Tokamak experiments in JT-60U and JFT-2M

Takizuka, Tomonori; Miura, Yukitoshi; JT-60 Team; JFT-2M Team

Chinese Physics Letters, 362, p.9 - 13, 1999/00

no abstracts in English

Journal Articles

Studies of boundary plasmas and fueling on the JFT-2M

Ogawa, Hiroaki; Miura, Yukitoshi; Fukumoto, Naoyuki*; Hasegawa, Koichi; Kawashima, Hisato; Maeno, Masaki; Nagata, Masayoshi*; Sengoku, Seio; Shibata, Takatoshi; Kasai, Satoshi; et al.

Journal of Nuclear Materials, 266-269, p.623 - 628, 1999/00

 Times Cited Count:12 Percentile:66.07(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Cyclotron

Arakawa, Kazuo

Kasokuki No Genjo To Shorai, (6), p.71 - 80, 1998/06

no abstracts in English

Journal Articles

Development of a power divider in the H plane using posts in a rectangular waveguide for the next generation lower hybrid current drive antenna

Seki, Masami; Maebara, Sunao; *; Ikeda, Yoshitaka; Imai, Tsuyoshi; *; *

Fusion Engineering and Design, 36(2-3), p.281 - 287, 1997/00

no abstracts in English

Journal Articles

Compact torus injection experiments on the H.I.T. test stand and the JFT-2M tokamak

Fukumoto, Naoyuki*; Fujiwara, Makoto*; Kuramoto, Keiji*; Ageishi, Masaya*; Nagata, Masayoshi*; Uyama, Tadao*; Ogawa, Hiroaki; Kasai, Satoshi; Hasegawa, Koichi; Shibata, Takatoshi

Proceedings of American Physical Society 39th Annual Meeting of the Division of Plasma Physics, 1 Pages, 1997/00

no abstracts in English

Journal Articles

Integral-type small reactor MRX and its applications

Shimazaki, Junya; Ochiai, Masaaki; Ishida, Toshihisa; Hoshi, Tsutao

10th Pacific Basin Nuclear Conf. (10-PBNC), p.828 - 833, 1996/00

no abstracts in English

JAEA Reports

An Examination on the determination precision of uranium content in the HTGR fuel compacts

Kobayashi, Fumiaki; Ito, Mitsuo; Suzuki, Shuichi*; Fukuda, Kosaku; *

JAERI-M 92-046, 18 Pages, 1992/04

JAERI-M-92-046.pdf:0.64MB

no abstracts in English

38 (Records 1-20 displayed on this page)