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Journal Articles

High-temperature rupture failure of high-burnup LWR-MOX fuel under a reactivity-initiated accident condition

Taniguchi, Yoshinori; Mihara, Takeshi; Kakiuchi, Kazuo; Udagawa, Yutaka

Annals of Nuclear Energy, 195, p.110144_1 - 110144_11, 2024/01

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Journal Articles

High-temperature gaseous reaction of cesium with siliceous thermal insulation; The Potential implication to the provenance of enigmatic Fukushima cesium-bearing material

Rizaal, M.; Nakajima, Kunihisa; Saito, Takumi*; Osaka, Masahiko; Okamoto, Koji*

ACS Omega (Internet), 7(33), p.29326 - 29336, 2022/08

 Times Cited Count:2 Percentile:29.84(Chemistry, Multidisciplinary)

Journal Articles

Behavior of high-burnup LWR-MOX fuel under a reactivity-initiated accident condition

Taniguchi, Yoshinori; Udagawa, Yutaka; Mihara, Takeshi; Amaya, Masaki; Kakiuchi, Kazuo

Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), p.551 - 558, 2019/09

Journal Articles

Effect of nitrogen concentration on nano-structure and high-temperature strength of 9Cr-ODS steel

Oka, Hiroshi; Tanno, Takashi; Otsuka, Satoshi; Yano, Yasuhide; Kaito, Takeji

Nuclear Materials and Energy (Internet), 16, p.230 - 237, 2018/08

 Times Cited Count:4 Percentile:38.58(Nuclear Science & Technology)

Journal Articles

High-pressure-high-temperature study of benzene; Refined crystal structure and new phase diagram up to 8 GPa and 923 K

Chanyshev, A. D.*; Litasov, K. D.*; Rashchenko, S.*; Sano, Asami; Kagi, Hiroyuki*; Hattori, Takanori; Shatskiy, A. F.*; Dymshits, A. M.*; Sharygin, I. S.*; Higo, Yuji*

Crystal Growth & Design, 18(5), p.3016 - 3026, 2018/05

 Times Cited Count:19 Percentile:84.86(Chemistry, Multidisciplinary)

The high-temperature structural properties of solid benzene were studied at 1.5-8.2 GPa up to melting or decomposition using multi-anvil apparatus and in situ neutron and X-ray diffraction. The crystal structure of deuterated benzene phase II (P2$$_{1}$$/c unit cell) was refined at 3.6-8.2 GPa and 473-873 K. Our data show a minor temperature effect on the change in the unit cell parameters of deuterated benzene at 7.8-8.2 GPa. At 3.6-4.0 GPa, we observed the deviation of deuterium atoms from the benzene ring plane and minor zigzag deformation of the benzene ring, enhancing with the temperature increase caused by the displacement of benzene molecules and decrease of van der Waals bond length between the $$pi$$-conjuncted carbon skeleton and the deuterium atom of adjacent molecule. Deformation of benzene molecule at 723-773 K and 3.9-4.0 GPa could be related to the benzene oligomerization at the same conditions. In the pressure range of 1.5-8.2 GPa, benzene decomposition was defined between 773-923 K. Melting was identified at 2.2 GPa and 573 K. Quenched products analyzed by Raman spectroscopy consist of carbonaceous material. The defined benzene phase diagram appears to be consistent with those of naphthalene, pyrene, and coronene at 1.5-8 GPa.

Journal Articles

Effect of thermo-mechanical treatments on nano-structure of 9Cr-ODS steel

Oka, Hiroshi; Tanno, Takashi; Otsuka, Satoshi; Yano, Yasuhide; Uwaba, Tomoyuki; Kaito, Takeji; Onuma, Masato*

Nuclear Materials and Energy (Internet), 9, p.346 - 352, 2016/12

 Times Cited Count:21 Percentile:88.83(Nuclear Science & Technology)

JAEA Reports

Design and installation of high-temperature ultrasonic measuring system and grinder for nuclear fuel containing trans-uranium elements

Serizawa, Hiroyuki; Kikuchi, Hironobu; Iwai, Takashi; Arai, Yasuo; Kurosawa, Makoto; Mimura, Hideaki; Abe, Jiro

JAERI-Tech 2005-039, 23 Pages, 2005/07

JAERI-Tech-2005-039.pdf:2.89MB

A high-temperature ultrasonic measuring system had been designed and installed in a glovebox (711-DGB) to study a mechanical property of nuclear fuel containing trans-uranium (TRU) elements. A figuration apparatus for the cylinder-type sample preparation had also been modified and installed in an established glovebox (142-D). The system consists of an ultrasonic probe, a heating furnace, cooling water-circulating system, a cooling air compressor, vacuum system, gas supplying system and control system. An A/D converter board and an pulsar/Receiver board for the measurement of wave velocity were installed in a personal computer. The apparatus was modified to install into the glovebox. Some safety functions were supplied to the control system. The shape and size of the sample was revised to minimize the amount of TRU elements for the use of the measurement. The maximum sample temperature is 1500 $$^{circ}$$C. The performance of the installed apparatuses and the glovebox were confirmed through a series of tests.

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

Irradiation Assisted Stress Corrosion Cracking (IASCC)

Tsukada, Takashi

Zairyo To Kankyo, 52(2), p.66 - 72, 2003/02

Irradiation assisted stress corrosion cracking (IASCC) is a potential failure mode suffered by the core-components of austenitic stainless steels in the aged light-water reactor (LWR), which is the intergranular type cracking caused by synergistic effects of neutron/gamma radiation and chemical environment. Effects of radiation on the materials and high-temperature water are discussed in this paper to understand IASCC phenomenon from a mechanistic viewpoint. It is essential to elucidate the radiation-induced microcompositional and microstructural changes in the alloy for mechanistic and predictive investigations of IASCC. Although grain boundary segregations of alloying and impurity elements are significant factors affecting IASCC, it has been considered that the radiation-induced microstructural and mechanical changes of materials play critical roles in IASCC. For mechanistic understanding of IASCC, further fundamental research works with experimental and theoretical approaches are needed. Efforts directed to the researches at the Japan Atomic Energy Research Institute are also described.

JAEA Reports

Radiation monitoring data of the HTTR rise-to-power test; Results up to 30 MW operation on the rated operation mode

Ashikagaya, Yoshinobu; Yoshino, Toshiaki; Yasu, Katsuji; Kurosawa, Yoshiaki; Sawa, Kazuhiro

JAERI-Tech 2002-094, 80 Pages, 2002/12

JAERI-Tech-2002-094.pdf:12.8MB

no abstracts in English

Journal Articles

Weapon-grade plutonium burning with HTRs

Yamane, Tsuyoshi; Yamashita, Kiyonobu; Fujimoto, Nozomu

New approaches to the nuclear fuel cycles and related disposal schemes, 1, p.267 - 277, 1998/00

no abstracts in English

Journal Articles

Dissolution of ThO$$_{2}$$-based oxides in nitric acid solutions at elevated temperatures

Akabori, Mitsuo; Shiratori, Tetsuo

Journal of Nuclear Science and Technology, 31(6), p.539 - 545, 1994/06

 Times Cited Count:16 Percentile:78.48(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Core void fraction distribution under high-temperature high-pressure boil-off conditions; Experimental study with two-phase flow test facility(TPTF)

; Kumamaru, Hiroshige; Murata, Hideo; Anoda, Yoshinari; Kukita, Yutaka

JAERI-M 93-200, 56 Pages, 1993/10

JAERI-M-93-200.pdf:1.85MB

no abstracts in English

Journal Articles

Fusion plasma diagnostics by LIDAR Thomson scattering

*; *; Matoba, Toru; Yamamoto, Shin

Reza Kenkyu, 20(6), p.375 - 391, 1992/06

no abstracts in English

Journal Articles

Application of new design methodologies to very high-temperature metallic components of the HTTR

Hada, Kazuhiko; Okubo, Minoru; Baba, Osamu

Nucl. Eng. Des., 132, p.13 - 21, 1991/00

 Times Cited Count:1 Percentile:19.91(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Developments of metallic materials and a high-temperature structural design code for the HTTR

Hada, Kazuhiko; Nishiguchi, Isoharu; ; Tsuji, Hirokazu

Nucl. Eng. Des., 132, p.1 - 11, 1991/00

 Times Cited Count:24 Percentile:90.25(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Vaporization of silver-indium-cadmium control rod material in flowing argon at high temperatures

Uetsuka, Hiroshi;

JAERI-M 89-150, 27 Pages, 1989/10

JAERI-M-89-150.pdf:0.67MB

no abstracts in English

Journal Articles

Sudies on thermal and hydraulic performance of fuel stack of VHTR, Part III; Experimental and analytical results of HENDEL multi-channel test rig with 12 independently heated fuel rods

; ; ; ; ;

Nihon Genshiryoku Gakkai-Shi, 29(2), p.133 - 140, 1987/02

 Times Cited Count:1 Percentile:19.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Change in electrical resistance of irradiated nuclear graphite during compressive tests

Journal of Nuclear Materials, 138, p.131 - 134, 1986/00

 Times Cited Count:0 Percentile:0.36(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Oxidation of 304 stainless steel in high-temperature steam

; ; Yaguchi, Shinnosuke*

Journal of Nuclear Materials, 140, p.74 - 84, 1986/00

 Times Cited Count:20 Percentile:86.83(Materials Science, Multidisciplinary)

no abstracts in English

30 (Records 1-20 displayed on this page)