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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.

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:17 Percentile:77.48(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

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, , 

6 (Records 1-6 displayed on this page)
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