Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 24

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

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

Development of creep property equations of 316FR stainless steel and Mod.9Cr-1Mo steel for sodium-cooled fast reactor to achieve 60-year design life

Onizawa, Takashi; Hashidate, Ryuta

Mechanical Engineering Journal (Internet), 6(1), p.18-00477_1 - 18-00477_15, 2019/02

Aiming at enhancing its economic competitiveness and reducing radioactive waste, JAEA has proposed an attractive plant concept and made great efforts to demonstrate the applicability of some innovative technologies to the plant. One of the most practical means is to extend the design life to 60 years. Accordingly, the material strength standards set by JSME have to be extended from 300,000 to 500,000 hours but this extension requires more precise estimation of creep rupture strength and creep strain of the materials in the long term. This paper describes the development of creep property equations of 316FR stainless steel and Mod.9Cr-1Mo steel considering changes in creep mechanisms at high temperatures in the long term based on evaluations of long-term creep properties of the materials. The creep property equations developed in this study will provide more precise estimation of the creep properties in the long term than the present creep property equations of JSME.

JAEA Reports

Cladding tube burst experiment assumed MA fuel pin for transmutation physics experimental facility

Sugawara, Takanori; Tsujimoto, Kazufumi

JAEA-Research 2017-011, 35 Pages, 2017/10

JAEA-Research-2017-011.pdf:4.88MB

The construction of Transmutation Physics Experimental Facility (TEF-P) is planned in the J-PARC project. TEF-P is a critical assembly and it will treat minor actinide (MA) fuel in the experiment. The temperature when the air cooling for the TEF-P core would stop was estimated but there were no data to evaluate the soundness of the MA fuel pin. To set a tentative limit temperature for the TEF-P core, cladding tube burst experiment was performed. As the result, the cladding tube burst occurred at 660$$^{circ}$$C as the severest case. Through these results and the estimation of creep rupture time, the tentative limit temperature for the TEF-P core was set to 600$$^{circ}$$C.

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:14 Percentile:73.52(Materials Science, Multidisciplinary)

no abstracts in English

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

Creep properties of 20% cold-worked Hastelloy XR

Kurata, Yuji; Nakajima, Hajime

Journal of Nuclear Materials, 228, p.176 - 183, 1996/00

 Times Cited Count:12 Percentile:71.65(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Long-term creep properties of Hastelloy XR in simulated high-temperature gas-cooled reactor helium

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

Journal of Nuclear Science and Technology, 32(11), p.1108 - 1117, 1995/11

 Times Cited Count:3 Percentile:37.69(Nuclear Science & Technology)

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

JAEA Reports

Creep behaviour of Hastelloy XR in simulated high-temperature gas-cooled reactor helium

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

JAERI-Research 95-037, 42 Pages, 1995/06

JAERI-Research-95-037.pdf:2.04MB

no abstracts in English

Journal Articles

Temperature dependence of creep properties of cold-worked Hastelloy XR

Kurata, Yuji; Nakajima, Hajime

Journal of Nuclear Science and Technology, 32(6), p.539 - 546, 1995/06

 Times Cited Count:6 Percentile:55.97(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Effect of cold work on creep properties of Hastelloy XR

Kurata, Yuji; Nakajima, Hajime

JAERI-Research 94-004, 30 Pages, 1994/08

JAERI-Research-94-004.pdf:2.99MB

no abstracts in English

JAEA Reports

Creep properties of 20% cold worked Hastelloy XR

Kurata, Yuji; Nakajima, Hajime

JAERI-M 94-022, 28 Pages, 1994/02

JAERI-M-94-022.pdf:0.9MB

no abstracts in English

Journal Articles

Effect of cold work on creep properties of Ni-22Cr-18Fe-9Mo alloy

Kurata, Yuji; Hamada, Shozo; Nakajima, Hajime

Proc. of 10th Int. Conf. on Strength of Materials; ICSMA 10, 0, p.677 - 680, 1994/00

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

Journal Articles

Improvement of creep resistance of a Ni base superalloy and its weld metal by controlling boron content

; *; *; *; Kondo, Tatsuo

Proc.Int.Conf.on Creep, p.97 - 102, 1986/00

no abstracts in English

Journal Articles

Creep and rupture behaviour of a special grade Hastelloy X in simulated HTGR helium

; Ogawa, Yutaka; Kondo, Tatsuo

Nuclear Technology, 66, p.250 - 259, 1984/00

 Times Cited Count:9 Percentile:68.72(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Creep test of type 304 stainless steel tube containg a notch subjected to internal pressure

Ueda, Shuzo; ;

Int.J.Press.Vessels Piping, 10, p.465 - 480, 1982/00

 Times Cited Count:1 Percentile:61.96(Engineering, Multidisciplinary)

no abstracts in English

JAEA Reports

Creep Test of Type 304 Stainless Steel Cylindrical Tube Subjected to Internal Pressure

Ueda, Shuzo; ;

JAERI-M 9647, 22 Pages, 1981/08

JAERI-M-9647.pdf:0.77MB

no abstracts in English

24 (Records 1-20 displayed on this page)