Investigation of kinetic recovery process in low dose neutron-irradiated nuclear graphite by thermal annealing-Reference-Cited by-同舟云学术

Investigation of kinetic recovery process in low dose neutron-irradiated nuclear graphite by thermal annealing

Published:2019-04-14 Issue:6 Volume:56 Page:533-540
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Jin Yuhao¹²³^ORCID,Yoshida Katsumi²^ORCID,Li Zhengcao¹^ORCID,Ai Desheng³,Maruyama Tadashi¹,Yano Toyohiko²^ORCID

Affiliation:

1. State Key Lab of New Ceramic and Fine Processing, Key Laboratory of Advanced Materials (MOE), School of Materials Science & Engineering, Tsinghua University, Beijing, China

2. Laboratory for Advanced Nuclear Energy, Institute of Innovative Research, Tokyo Institute of Technology, Meguro-ku, Tokyo, Japan

3. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, China

Funder

China National Science and Technology Major Project

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2019.1602570

Reference24 articles.

1. Investigation on structural integrity of graphite component during high temperature 950 °C continuous operation of HTTR

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

3. Present knowledge about the materials behavior in JT-60

4. Dimensional changes in the irradiated graphite lattice

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