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Journal Articles

Microstructural stability of ODS steel after very long-term creep test

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

Journal of Nuclear Materials, 547, p.152833_1 - 152833_7, 2021/04

 Times Cited Count:3 Percentile:72.48(Materials Science, Multidisciplinary)

In order to evaluate the stability of nano-sized oxide particles and matrix structure of ODS cladding tube, which are the determinants of their high temperature strength, the microstructural observation was carried out after internal pressurized creep test at 700$$^{circ}$$C for over 45,000 hours. The specimens were the as-received and crept specimens of 9Cr-ODS steel with tempered martensite and 12Cr-ODS steel with recrystallized ferrite. Small platelet was cut out from the crept pressurized tube, then thinned to foil. Microstructural observation was conducted with TEM JEOL 2010F. As a result of the observation, it was confirmed that the size and number density of the nano-sized particles were almost unchanged even after the creep test. In addition, the tempered martensite structure, which is one of the determinants of the creep strength of 9Cr-ODS steel, was not significantly different between the as-received and crept specimen, indicating the stability of their matrix structure.

Journal Articles

Evaluation of breach characteristics of fast reactor fuel pins during steady state irradiation

Oka, Hiroshi*; Kaito, Takeji; Ikusawa, Yoshihisa; Otsuka, Satoshi

Nuclear Engineering and Design, 370, p.110894_1 - 110894_8, 2020/12

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

The objective of this study is to evaluate the reliability of a cumulative damage fraction (CDF) analysis for the prediction of fuel pin breach in fast rector using experimentally obtained fuel pin breach data for the first time. Six breached fuel pins were obtained from steady state irradiation in the EBR-II. Post irradiation examinations revealed that FP gas pressure was the main cause of creep damage in cladding, and that the stress contribution from FCMI was negligible. CDFs evaluated for these pins using in-reactor creep rupture equation, taking into account the irradiation history of cladding temperature and hoop stress due to FP gas pressure, were in the range of 0.7 to 1.4 at the occurrence of breach. This shows clearly that fuel pin breach occurs when the CDF approaches 1.0. The results indicate that CDF analysis would be a reliable method for the prediction of fuel pin breach when appropriate material strength and environmental effects are adopted.

Journal Articles

Creep behavior and microstructure for two-dimensional C/C composite

Shibata, Taiju; Baba, Shinichi; Yamaji, Masatoshi*; Sumita, Junya; Ishihara, Masahiro

Nihon Kikai Gakkai M&M 2004 Zairyo Rikigaku Kanfarensu Koen Rombunshu, p.407 - 408, 2004/00

no abstracts in English

Journal Articles

Development of a filler metal for weldments of a Ni-Cr-W superalloy with high creep strength

Kurata, Yuji; Saito, T.*; Tsuji, Hirokazu; Takatsu, T.*; Shindo, Masami; Nakajima, Hajime

JSME International Journal, Series A, 45(1), p.104 - 109, 2002/01

no abstracts in English

Journal Articles

Development of a filler metal for weldments of a Ni-Cr-W superalloy with high creep strength

Kurata, Yuji; Saito, T.*; Tsuji, Hirokazu; Takatsu, T.*; Shindo, Masami; Nakajima, Hajime

Proceedings of the 7th International Conference on Creep and Fatigue at Elevated Temperatures (CREEP7), p.93 - 99, 2001/06

no abstracts in English

Journal Articles

Development of a filler metal for weldments of a Ni-Cr-W superalloy with superior creep strength

Kurata, Yuji; Saito, T.*; Tsuji, Hirokazu; Takatsu, T.*; Shindo, Masami; Nakajima, Hajime

Nihon Gakujutsu Shinkokai Genshiro Zairyo Dai-122-Iinkai Shiryoshu, p.279 - 282, 2000/11

no abstracts in English

JAEA Reports

Creep rupture properties of trial welded joints of a Ni-Cr-W superalloy in air environment

; Saito, T.*; Tsuji, Hirokazu; Takatsu, T.*; Shindo, Masami; Nakajima, Hajime

JAERI-Research 97-032, 20 Pages, 1997/05

JAERI-Research-97-032.pdf:1.78MB

no abstracts in English

Journal Articles

Creep rupture properties of a Ni-Cr-W superalloy in air environment

; Tsuji, Hirokazu; Shindo, Masami; Nakajima, Hajime

Journal of Nuclear Materials, 246(2-3), p.196 - 205, 1997/00

 Times Cited Count:16 Percentile:76.66(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Long-term creep and rupture behavior of Hastelloy XR in simulated high-temperature gas-cooled reactor helium

Kurata, Yuji; *; ; Shindo, Masami; Nakajima, Hajime; *

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 36(2), p.149 - 156, 1995/07

no abstracts in English

Journal Articles

Exploratory study on providing austenitic stainless steels designed for nuclear applications

Nakajima, Hajime; *; Watanabe, Katsutoshi; Kondo, Tatsuo

Computer Aided Innovation of New Materials, p.827 - 830, 1991/00

no abstracts in English

Journal Articles

The crack initiation and growth behavior for high temperature creep-fatigue interaction in notched specimen of Ni-based alloy

; *; ;

Nihon Kikai Gakkai Rombunshu, A, 52(477), p.1228 - 1231, 1986/00

no abstracts in English

Oral presentation

Evaluation of breach characteristics of fast reactor fuel pins during steady state irradiation

Oka, Hiroshi; Ikusawa, Yoshihisa; Otsuka, Satoshi; Kaito, Takeji

no journal, , 

12 (Records 1-12 displayed on this page)
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