High Temperature Corrosion Studies of Metallic Materials in High Temperature Gas-Cooled Nuclear Reactor Helium Environment

Made available in DSpace on 2017-07-06T18:55:04Z (GMT). No. of bitstreams: 3 Lee_Daniel_K_MS.pdf: 75457165 bytes, checksum: 1c352f8a0eaf27a3c60286c777a82659 (MD5) Lee_Daniel_K_MS_ABS.pdf: 628459 bytes, checksum: 9adc2363b16d312ea8d65075fd1b4b1f (MD5) license.txt: 4813 bytes, checksum: 715c4321821a960fa1a1e91d2ac7ebce (MD5) Previous issue date: 1983

Name thesis:degree_name

M.S. (master's)

Level thesis:degree_level

Thesis

Discipline thesis:degree_discipline

Nuclear, Plasma, and Radiological Engineering

Year dc:date

2017

Author dc:creator

• Lee, Daniel K.

• nuclear engineering
• high temperature corrosion
• metallic materials
• nuclear reactor helium environment
• high temperature gas cooled reactors
• HTGR
• oxidation
• carburization
• alloy 800H
• hastelloy X
• type 310 stainless steel
• ductility

Statement dc:rights

• Copyright 1997 Erik Stefan Kirstein

Language dc:language

en

Handle dc:identifier

http://hdl.handle.net/2142/96429

OAI identifier oai:identifier

oai:www.ideals.illinois.edu:2142/96429