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Journal of Nuclear Science and Technology Volume 47, 2010 - Issue 7
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ARTICLE

Interpolation and Extrapolation Method to Analyze Irradiation-Induced Dimensional Change Data of Graphite for Design of Core Components in Very High Temperature Reactor (VHTR)

Taiju SHIBATA Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Higashi-ibaraki-gun, Ibaraki, 311-1393, Japan
,
Eiji KUNIMOTO Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Higashi-ibaraki-gun, Ibaraki, 311-1393, Japan
,
Motokuni ETO Toyo Tanso Co., Ltd., 2791 Matsusaki, Takuma-cho, Mitoyo-shi, Kagawa, 769-1102, Japan
,
Shusaku SHIOZAWA Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Higashi-ibaraki-gun, Ibaraki, 311-1393, Japan
,
Kazuhiro SAWA Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Higashi-ibaraki-gun, Ibaraki, 311-1393, Japan
,
Tatsuo OKU Ibaraki University, Japan
&
Tadashi MARUYAMA Tokyo Institute of Technology, 2-12-1-N1-13 Ookayama, Meguro-ku, Tokyo, 152-8550, Japan
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Pages 591-598 | Received 11 Sep 2009, Accepted 11 Feb 2010, Published online: 05 Jan 2012

Citations (10)

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Read on this site (2)

Yuhao Jin, Katsumi Yoshida, Zhengcao Li, Desheng Ai, Tadashi Maruyama & Toyohiko Yano. (2019) Investigation of kinetic recovery process in low dose neutron-irradiated nuclear graphite by thermal annealing. Journal of Nuclear Science and Technology 56:6, pages 533-540.
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Yuhao Jin, Katsumi Yoshida, Zhengcao Li, Tadashi Maruyama & Toyohiko Yano. (2017) Precision dilatometer analysis of neutron-irradiated nuclear graphite recovery process up to 1673 K. Journal of Nuclear Science and Technology 54:4, pages 424-431.
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Articles from other publishers (8)

Zhihan Hu, Di Chen, SeungSu Kim, Rijul Chauhan, Yongchang Li & Lin Shao. (2022) Effect of Stress on Irradiation Responses of Highly Oriented Pyrolytic Graphite. Materials 15:10, pages 3415.
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Makuteswara Srinivasan. (2021) Analysis and evaluation of the irradiated dimensional and volume change behavior of nuclear graphites. Nuclear Engineering and Design 381, pages 111354.
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Guifeng Zhu, Wei Guo, Xuzhong Kang, Chunyan Zou, Yang Zou, Rui Yan & Ye Dai. (2020) Neutronic effect of graphite dimensional change in a small modular molten salt reactor. International Journal of Energy Research 45:8, pages 11976-11991.
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Steve Johns, Lingfeng He, Karen Bustillo, William E. Windes, Rick Ubic & Chinnathambi Karthik. (2020) Fullerene-like defects in high-temperature neutron-irradiated nuclear graphite. Carbon 166, pages 113-122.
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Yuji Fukaya, Naoki Mizuta, Minoru Goto, Hirofumi Ohashi & Xing L. Yan. (2020) Conceptual design study of a high performance commercial HTGR for early introduction. Nuclear Engineering and Design 361, pages 110577.
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Michio Inagaki, Feiyu Kang, Masahiro Toyoda & Hidetaka Konno. 2014. Advanced Materials Science and Engineering of Carbon. Advanced Materials Science and Engineering of Carbon 387 410 .
Taiju Shibata. 2013. Handbook of Advanced Ceramics. Handbook of Advanced Ceramics 113 123 .
Xinmei Yang, Shanglei Feng, Xingtai Zhou, Hongjie Xu & T. K. Sham. (2012) Interaction between Nuclear Graphite and Molten Fluoride Salts: A Synchrotron Radiation Study of the Substitution of Graphitic Hydrogen by Fluoride Ion. The Journal of Physical Chemistry A 116:3, pages 985-989.
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