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Journal Articles

Federated learning of creep rupture time and high temperature tensile strength prediction models

Sakurai, Junya*; Torigata, Keisuke*; Matsunaga, Manabu*; Takanashi, Naoto*; Hibino, Shinya*; Kizu, Kenichi*; Morita, Akira*; Inomoto, Masahiro*; Shimohata, Nobuaki*; Toyota, Kodai; et al.

Tetsu To Hagane, 111(5), p.246 - 262, 2025/04

JAEA Reports

High-temperature strength of modified type 316 steel for fast reactor fuel before and after neutron irradiation

Miyazawa, Takeshi; Uwaba, Tomoyuki; Yano, Yasuhide; Tanno, Takashi; Otsuka, Satoshi; Onizawa, Takashi; Ando, Masanori; Kaito, Takeji

JAEA-Technology 2024-009, 140 Pages, 2024/10

JAEA-Technology-2024-009.pdf:8.03MB

For the purpose of enhancing the reliability of fast reactor fuel designing using modified type 316 steel, the out-of-pile and in-pile mechanical data of modified type 316 steel cladding tubes and wrapper tubes were statistically analyzed with the knowledge on material science and engineering; the high-temperature strength equations of modified type 316 steel, which can be applied to high-dose neutron irradiation environment, were derived. The out-of-pile high-temperature tensile and creep data of modified type 316 steel cladding tubes and wrapper tubes were derived up to 900$$^{circ}$$C, which is higher than the upper limit temperature of anticipated transient event of fast reactor. Using the extended database, the best-fit equation and the lower limit equation were derived for out-of-pile 0.2% proof strength, ultimate tensile strength and creep rupture strength while the best-fit equation and the upper and lower limit equations for creep strain. Furthermore, the degradation factors for tensile and creep strength, which will be produced by in-reactor environment (i.e., neutron irradiation in liquid sodium), were evaluated using the existing neutron irradiation data of modified type 316 steel, which were derived using the experimental fast reactor Joyo, the French proto-type fast reactor Phenix, the American experimental fast reactor FFTF. The derived equations were validated by the comparison with the experimental data.

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:33.30(Nuclear Science & Technology)

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:22 Percentile:87.06(Nuclear Science & Technology)

Journal Articles

Residual stress evaluation of butt weld sample of high tensile strength steel using neutron diffraction

Suzuki, Hiroshi; Holden, T. M.*; Moriai, Atsushi; Minakawa, Nobuaki*; Morii, Yukio

Zairyo, 54(7), p.685 - 691, 2005/07

no abstracts in English

Journal Articles

High temperature bending characteristics of Al$$_{2}$$O$$_{3}$$ joints bonded using superplastic ceramics as interlayer

Sato, Takashi*; Motohashi, Yoshinobu*; Sakuma, Takaaki*; Waseda, Kazuyoshi*; Shibata, Taiju; Ishihara, Masahiro; Sawa, Kazuhiro

Nihon Kikai Gakkai Kanto Shibu Ibaraki Koenkai (2004) Koen Rombunshu (No.040-3), p.55 - 56, 2004/09

no abstracts in English

JAEA Reports

Influence of hydrogen absorption and neutron irradiation on mechanical properties of zircaloy-4 and MDA (Joint research)

Nagase, Fumihisa; Sugano, Mitsuteru*; Ozawa, Masaaki*; Komatsu, Kazushi*; Furuta, Teruo*

JAERI-Research 2001-008, 61 Pages, 2001/03

JAERI-Research-2001-008.pdf:2.62MB

no abstracts in English

Journal Articles

Damage structures and mechanical properties in high-purity Fe-9Cr alloy irradiated by neutrons

Wakai, Eiichi; Hishinuma, Akimichi; Usami, Koji; Kato, Yasushi*; Takaki, Seiichi*; Abiko, Kenji*

Materials Transactions, JIM, 41(9), p.1180 - 1183, 2000/09

no abstracts in English

Journal Articles

Strength test of C/C composite high performance control rod for HTGRs

Ishiyama, Shintaro; Fukaya, Kiyoshi; Eto, Motokuni

Nihon Genshiryoku Gakkai-Shi, 41(10), p.1092 - 1099, 1999/00

 Times Cited Count:2 Percentile:20.92(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of divertor plate with CFCs bouded onto DSCu cooling tube for fusion reactor application

; ; Araki, Masanori; Nakamura, Kazuyuki; Akiba, Masato

Journal of Nuclear Materials, 258-263, p.318 - 322, 1998/00

 Times Cited Count:8 Percentile:56.62(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development of high strength austenitic stainless steel for conduit of Nb$$_{3}$$Al conductor

Nakajima, Hideo; Nunoya, Yoshihiko; O.Ivano*; Ando, Toshinari; Kawasaki, T.*; Hanawa, Hiromi*; Seki, Shuichi*; Takano, Katsutoshi*; Tsuji, Hiroshi; ; et al.

Advances in Cryogenic Engineering Materials, Vol.42, p.323 - 330, 1996/00

no abstracts in English

Journal Articles

Development status of structural materials for superconducting coils of fusion reactor

Nakajima, Hideo

Yosetsu Gakkai-Shi, 64(3), p.168 - 171, 1995/00

no abstracts in English

Journal Articles

High temperature Youngs modulus of a fine-grained nuclear graphite oxidized or prestressed to various levels

Eto, Motokuni; Oku, Tatsuo; Konishi, Takashi*

Carbon, 29(1), p.11 - 21, 1991/01

 Times Cited Count:26 Percentile:75.24(Chemistry, Physical)

no abstracts in English

Journal Articles

Strength and Youngs modulus of silicon carbide layers of HTGR fuel particles at high temperatures

Minato, Kazuo; Fukuda, Kosaku

Journal of Nuclear Materials, 182, p.6 - 10, 1991/00

 Times Cited Count:3 Percentile:40.38(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Effect of molecular orientation on the radiolysis of polyethylene in the presence of oxygen

; Nishii, Masanobu; Seguchi, Tadao; ;

Radiation Physics and Chemistry, 37(2), p.213 - 216, 1991/00

no abstracts in English

Journal Articles

Elastic modulus and bend strength of a nuclear graphite at high temperature

; ;

Carbon, 25(6), p.723 - 726, 1987/06

 Times Cited Count:27 Percentile:75.17(Chemistry, Physical)

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:0.00(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

High Temperatune Alloys and Ceramics Heat Exchanga

JAERI-M 84-080, 40 Pages, 1984/04

JAERI-M-84-080.pdf:1.36MB

no abstracts in English

22 (Records 1-20 displayed on this page)