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Candidate Materials Evaluation for the Supercritical Water-Cooled Reactor
A Mechanistic Basis for Irradiation Assisted Stress Corrosion Cracking
Accelerator-Based Study of Irradiation Creep of Pyrolytic Carbon Used in TRISO Fuel Particles for Very High Temperature Reactors (VHTR)
Acquisition of a Research Grade Ion Implanter for Research and Education in Ion Beam Modification of Materials
Alloys for 1000°C Service in the Next Generation Nuclear Plant
BWRVIP Highly Irradiated Stainless Steel Crack Growth
Consortium on Cladding and Structural Materials for Advanced Nuclear Energy Systems
Constant Extension Rate Testing of Alloy 690 in Supercritical Water
High Temperature Materials for the Gas-Cooled Fast Reactor
Localized Deformation as a Primary Cause of Irradiation Assisted Stress Corrosion Cracking
Radiation-Induced Segregation and Phase Stability in Candidate Alloys for the Advanced Burner Reactor
Stress Corrosion Cracking and Corrosion of Candidate Alloys for the Supercritical Water Reactor Concept
Stress Corrosion Cracking of Neutron Irradiated Cast Stainless Steels in High Temperature Water
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About: nlroth
Posts by nlroth:
Hello world!
Posted on
July 15, 2013
(June 22, 2021)
by
Michigan Engineering
in
Uncategorized
