Interaction between B4C, 304 stainless steel, and Zircaloy-4 in H2O/H2 atmosphere at 1473 K-Reference-Cited by-同舟云学术

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Interaction between B4C, 304 stainless steel, and Zircaloy-4 in H2O/H2 atmosphere at 1473 K

Published:2017-11-17 Issue:4 Volume:55 Page:400-409
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Gao Xu¹,Sasaki Ryosuke¹,Zheng Lichun¹,Ueda Shigeru¹,Kim Sun-joong²,Kitamura Shin-ya¹,Kobayashi Yoshinao³

Affiliation:

1. Institute of Multidisciplinary Research Advanced Material, Tohoku University, Aoba-ku, Sendai, Japan

2. Department of Materials Science and Engineering, Chosun University, Dong-gu, Gwangju, South Korea

3. Laboratory for Advanced Nuclear Energy, Tokyo Institute of Technology, Meguro-ku, Tokyo, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2017.1403388

Reference11 articles.

1. Reactor Core Materials Interactions at Very High Temperatures

2. Study of boron behaviour in the primary circuit of water reactors under severe accident conditions: A comparison of Phebus FPT3 results with other recent integral and separate-effects data

3. Oxidation of boron carbide at high temperatures

4. Influence of boron carbide on core degradation during severe accidents in LWRs

5. Reaction between B4C and austenitic stainless steel in oxidizing atmosphere at temperatures below 1673 K

Cited by 9 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Normal spectral emissivity, specific heat capacity, and thermal conductivity of type 316 austenitic stainless steel containing up to 10 mass% B4C in a liquid state;Journal of Nuclear Materials;2022-09

2. Chemical interactions between ZrO2/α-Zr structured Zircaloy-4 and 316 stainless steel-B4C melt at 1300 °C;Journal of Nuclear Materials;2022-02

3. Transient interactions of boron carbide with molten uranium oxide;Nuclear Materials and Energy;2021-12

4. Solidification and re-melting mechanisms of SUS-B4C eutectic mixture;Journal of Nuclear Materials;2021-01

5. Phase Diagram of Corium Systems;Comprehensive Nuclear Materials;2020

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