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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

Damage evaluation techniques for FBR and LWR structural materials based on magnetic and corrosion properties along grain boundaries

Hoshiya, Taiji*; Takaya, Shigeru*; Ueno, Fumiyoshi; Nemoto, Yoshiyuki; Nagae, Yuji*; Miwa, Yukio; Abe, Yasuhiro*; Omi, Masao; Tsukada, Takashi; Aoto, Kazumi*

Transactions of the Materials Research Society of Japan, 29(4), p.1687 - 1690, 2004/06

JAERI and JNC have begun the cooperative research of evaluation techniques of structural material degradation in FBR and LWR, which based on magnetic and corrosion properties along grain boundaries. Magnetic method has been proposed as the one of the non-destructive detection techniques on the early stage of creep-damage before crack initiation for aged structural materials of FBRs. The effects of applied stress on natural magnetization were investigated on paramagnetic stainless steels having creep-damages. On the other hand, corrosion properties and magneto-optical characteristics of ion-irradiated stainless steels in the vicinity of grain boundaries were estimated by AFM and Kerr effect microscope, respectively. These degradations were induced by changes in characteristics in the vicinity of grain boundaries. It is found that the initial level of progressing process of damage can detect changes in magnetic and corrosion properties along grain boundaries of aged and degraded nuclear plants structural materials.

JAEA Reports

Structural integrity assessment of intermediate heat exchanger in the HTTR based on results of rise-to-power test

Takeda, Takeshi; Tachibana, Yukio; Nakagawa, Shigeaki

JAERI-Tech 2002-091, 45 Pages, 2002/12

JAERI-Tech-2002-091.pdf:1.77MB

no abstracts in English

Journal Articles

Study on creep-fatigue life of irradiated austenitic stainless steel

Ioka, Ikuo; Miwa, Yukio; Tsuji, Hirokazu; Yonekawa, Minoru; Takada, Fumiki; Hoshiya, Taiji

JSME International Journal, Series A, 45(1), p.51 - 56, 2002/01

The low cycle creep-fatigue test with tensile strain hold of the austenitic stainless steel irradiated to 2dpa was carried out at 823K in vacuum. The applicability of creep-fatigue life prediction methods to the irradiated specimen was examined. The fatigue life on the irradiated specimen without tensile strain hold time was reduced by a factor of 2-5 in comparison with the unirradiated specimen. The fraction of intergranular fracture increased with increasing strain hold time. The decline in fatigue life of the irradiated specimen with tensile strain hold was almost equal to that of the unirradiated specimen. For the irradiated specimen, the time fraction damage rule trends to yield unsafe estimated lives and the ductility exhaustion damage rule trends to yield generous results. However, all of data were predicted within a factor of three on life by the linear damage rule.

Journal Articles

Creep damage in welded joints of a Ni-base heat-resistant alloy hastelloy XR

*; ; *; Tsuji, Hirokazu; *; Shindo, Masami

Mater. Sci. Eng., A, 234-236, p.1087 - 1090, 1997/00

no abstracts in English

Journal Articles

Structural design for intermediate heat exchanger of the HTTR

Kunitomi, Kazuhiko; Takeda, Takeshi; Shinozaki, Masayuki; Okubo, Minoru; *; Koikegami, Hajime*

Nihon Genshiryoku Gakkai-Shi, 37(4), p.316 - 326, 1995/00

 Times Cited Count:1 Percentile:17.89(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of designing method for intermediate heat exchanger in the HTTR

Kunitomi, Kazuhiko; Shinozaki, Masayuki; Okubo, Minoru; Koikegami, Hajime*; *

Proc. of ARS 94 Int. Topical Meeting on Advanced Reactors Safety,Vol. 1, 0, p.188 - 192, 1994/00

no abstracts in English

Journal Articles

Structural design method for high temperature serries and its application

;

Oyo Kikai Kogaku, 20(10), p.24 - 29, 1979/00

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, , 

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