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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
alloying design
fabrication tests
high temperature strength
neutron beams
irradiation resistance
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
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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