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Journal Articles

Effects of silicon, carbon and molybdenum additions on IASCC of neutron irradiated austenitic stainless steels

Nakano, Junichi; Miwa, Yukio; Koya, Toshio; Tsukada, Takashi

Journal of Nuclear Materials, 329-333(Part1), p.643 - 647, 2004/08

 Times Cited Count:9 Percentile:52.57(Materials Science, Multidisciplinary)

To study effects of minor elements on the irradiation assisted stress corrosion cracking (IASCC), high purity Type 304 and 316 stainless steels (SSs) were fabricated and added minor elements, Si or C. After neutron irradiation to 3.5$$times$$10$$^{25}$$n/m$$^{2}$$ (E$$>$$1MeV), the slow strain rate tests (SSRT) for the irradiated specimens was conducted in oxygeneted high purity water at 561 K. Fracture surface of the specimens was examined using the scanning electron microscope (SEM) after the SSRT. Fraction of intergranular stress corrosion cracking (IGSCC) on the fracture surface after the SSRT increased with netron fluence. Suppression of irradiation hardening and increase of peiod to SCC fracture as benefitical effects of the additional elements, Si or Mo, were not observed obviously. In high purity SS added C, fraction of IGSCC was the smallest in the all SSs, although irraidiation hardening level was the largest in the all SSs. Addition of C suppressed the susceptibility to IGSCC.

JAEA Reports

Proceedings of the 11th International Workshop on Ceramic Breeder Blanket Interactions; December 15 - 17, 2003, Tokyo, Japan

Enoeda, Mikio

JAERI-Conf 2004-012, 237 Pages, 2004/07

JAERI-Conf-2004-012.pdf:44.1MB

This report is the Proceedings of "the Eleventh International Workshop on Ceramic Breeder Blanket Interactions" which was held as a workshop on ceramic breeders Under the IEA Implementing Agreement on the Nuclear Technology of Fusion Reactors, and the Japan-US Fusion Collaboration Framework. In the workshop, information exchange was performed for designs of solid breeder blankets and test blankets in EU, Russia and Japan, recent results of irradiation tests, HICU, EXOTIC-8 and the irradiation tests by IVV-2M, modeling study on tritium release behavior of Li$$_{2}$$TiO$$_{3}$$ and other breeders, fabrication technology developments and characterization of the Li$$_{2}$$TiO$$_{3}$$ and Li$$_{4}$$SiO$$_{4}$$ pebbles, research on measurements and modeling of thermo-mechanical behaviors of Li$$_{2}$$TiO$$_{3}$$ and Li$$_{4}$$SiO$$_{4}$$ pebbles, and interfacing issues, such as, fabrication technology for blanket box structure, neutronics experiments of blanket mockups by fusion neutron source and tritium recovery system.

JAEA Reports

Neutronics analysis on helium production control in stainless steel by neutron spectral tailoring in the JMTR

Shimakawa, Satoshi; ; Nagao, Yoshiharu;

JAERI-Tech 95-023, 26 Pages, 1995/03

JAERI-Tech-95-023.pdf:1.08MB

no abstracts in English

JAEA Reports

Neutorn spectral tailoring calculation in the JMTR; Feasible study on irradiation test simulating the fusion reactor condition

Nagao, Yoshiharu; Shimakawa, Satoshi; ;

JAERI-Tech 95-006, 46 Pages, 1995/02

JAERI-Tech-95-006.pdf:1.45MB

no abstracts in English

Journal Articles

HTGR project and requirements from universities

Shiozawa, Shusaku

Kaigiroku: Kaku Yugoro Zairyo Foramu 9; Oarai Zairyo Shosha Kenkyukai, p.95 - 116, 1993/00

no abstracts in English

Oral presentation

Development for high-performance irradiation tests and PIE techniques with research/testing reactors

Tsuchiya, Kunihiko; Takeuchi, Tomoaki; Otsuka, Noriaki; Shibata, Hiroshi; Nakano, Hiroko; Ishida, Takuya; Uehara, Toshiaki; Yamamoto, Keiichi; Saito, Takashi; Nakamura, Jinichi; et al.

no journal, , 

no abstracts in English

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