A new perspective on density and strength loss profiles at the surface of thermally oxidized nuclear graphite-Reference-Cited by-同舟云学术

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A new perspective on density and strength loss profiles at the surface of thermally oxidized nuclear graphite

Published:2024-06 Issue: Volume:227 Page:119247
ISSN:0008-6223
Container-title:Carbon
language:en
Short-container-title:Carbon

Author:

Contescu Cristian I.^ORCID,Spicer James B.,Lin Lianshan^ORCID,Arregui-Mena Jose D.^ORCID,Gallego Nidia C.^ORCID

Funder

US Department of Energy

Publisher

Elsevier BV

Reference73 articles.

1. Design and manufacture of graphite components for 21st century small modular reactors;Srinivasan;Nucl. Eng. Des.,2022

2. Modular HTGR Safety Basis and Approach;Hicks,2011

3. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,2023

4. Gas-graphite systems;Clark,1962

5. Preliminary Safety Information Document for the Standard MHTGR, DOE/HTGR-86-024-Vol. 1,1986

Cited by 1 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. A review of research progress of graphite oxidation in high temperature gas-cooled reactors;Nuclear Engineering and Design;2024-11

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