高速炉炉心材料用改良オーステナイト鋼の開発

鹿倉, 栄; 鵜飼, 重治; 佐藤, 義則; 原田, 誠; 小山, 真一; 伊藤, 卓志; 野村, 茂雄; 芝原, 格

doi:10.3327/jaesj.36.441


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高速炉炉心材料用改良オーステナイト鋼の開発

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Title:	高速炉炉心材料用改良オーステナイト鋼の開発
Other Titles:	Development of Advanced Austenitic Stainless Steel for Fast Reactor Core Material
Authors:	鹿倉, 栄¹ Browse this author
	鵜飼, 重治² Browse this author
	佐藤, 義則³ Browse this author
	原田, 誠⁴ Browse this author
	小山, 真一⁵ Browse this author
	伊藤, 卓志⁶ Browse this author
	野村, 茂雄⁷ Browse this author
	芝原, 格⁸ Browse this author
Authors(alt):	Shikakura, Sakae¹
	Ukai, Shigeharu²
	Sato, Yoshinori³
	Harada, Makoto⁴
	Koyama, Shinichi⁵
	Ito, Takushi⁶
	Nomura, Shigeo⁷
	Shibahara, Itaru⁸
Keywords:	advanced austenitic steels
	PNC1520
	alloying design
	fabrication tests
	high temperature strength
	neutron beams
	irradiation resistance
	corrosion
	fission products
	Demonstration reactor
Issue Date:	30-May-1994
Publisher:	日本原子力学会
Journal Title:	日本原子力学会誌
Journal Title(alt):	Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
Volume:	36
Issue:	5
Start Page:	441
End Page:	455
Publisher DOI:	10.3327/jaesj.36.441
Abstract:	Advanced austenitic stainless steel beyond the standard composition region of SUS316 stainless steel PNC1520 has been successfully developed. Optimization of the steel leads to a composition of 15Cr-20Ni-0.06C-2.5Mo-1.7Mn-0.25Ti-0.1Nb-0.028P-0.004B through the alloying design and fabrication tests. An extensive series of evaluation tests including out-of-pile, sodium environment, neutron irradiation and fission product corrosion has confirmed that PNC1520 is superior in high temperature strength and irradiation resistance to PNC316 as a core material for the prototype reactor MONJU. PNC1520 is the best candidate material for the Demonstration reactor and will be tested on the whole core scale in JOYO MK-III to obtain the proven data.
Type:	article
URI:	http://hdl.handle.net/2115/76309
Appears in Collections:	工学院・工学研究院 (Graduate School of Engineering / Faculty of Engineering) > 雑誌発表論文等 (Peer-reviewed Journal Articles, etc)

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