Introduction • This research program is aimed at evaluating different types of environment-induced degradation of candidate target materials for applications in transmutation of spent nuclear fuels (SNF). • Transmutation refers to the elimination of long-lived actinides and fission products from SNF. Objectives • Evaluate susceptibility of candidate target materials to stress corrosion cracking (SCC) and localized corrosion (pitting and crevice) in neutral and acidic aqueous environments at ambient and elevated temperatures • Determine the extent and morphology of cracking in tested materials as functions of experimental and environmental variables including pH, temperature, loading conditions and specimen geometry • Develop mechanistic und...
Three martensitic candidate target materials, namely Alloys EP-823 and HT-9, and Type 422 stainless ...
Irradiation-assisted stress corrosion cracking is a costly degradation mechanism for austenitic stai...
During the use of nuclear reactors the properties of the structural materials change. Variations in ...
This paper presents the results of SCC tests of quenched and tempered martensitic Type 422 SS in neu...
The primary objective of this task is to evaluate the potential for the environmentally-assisted cra...
As indicated in the original proposal, the primary objective of this task was to evaluate the effect...
This paper presents the results of stress corrosion cracking (SCC) studies of two martensitic target...
As indicated in the original proposal, the primary objective of this task is to evaluate the effect ...
The primary objective of this task is to evaluate the effect of hydrogen on environment-assisted cra...
The primary objective of this task is to evaluate the effect of hydrogen on environment-assisted cra...
The primary objective of this task is to evaluate the effect of hydrogen on environment-assisted cra...
The subject task entitled “Hydrogen-Induced Embrittlement of Candidate Target Materials for Applicat...
As indicated in the original proposal, the primary objective of this task is to evaluate the effect ...
Spallation-neutron-sources, such as those under investigation for use in accelerator-driven transmut...
The disposal of high-level radioactive waste poses a severe challenge to all nuclear power-generatin...
Three martensitic candidate target materials, namely Alloys EP-823 and HT-9, and Type 422 stainless ...
Irradiation-assisted stress corrosion cracking is a costly degradation mechanism for austenitic stai...
During the use of nuclear reactors the properties of the structural materials change. Variations in ...
This paper presents the results of SCC tests of quenched and tempered martensitic Type 422 SS in neu...
The primary objective of this task is to evaluate the potential for the environmentally-assisted cra...
As indicated in the original proposal, the primary objective of this task was to evaluate the effect...
This paper presents the results of stress corrosion cracking (SCC) studies of two martensitic target...
As indicated in the original proposal, the primary objective of this task is to evaluate the effect ...
The primary objective of this task is to evaluate the effect of hydrogen on environment-assisted cra...
The primary objective of this task is to evaluate the effect of hydrogen on environment-assisted cra...
The primary objective of this task is to evaluate the effect of hydrogen on environment-assisted cra...
The subject task entitled “Hydrogen-Induced Embrittlement of Candidate Target Materials for Applicat...
As indicated in the original proposal, the primary objective of this task is to evaluate the effect ...
Spallation-neutron-sources, such as those under investigation for use in accelerator-driven transmut...
The disposal of high-level radioactive waste poses a severe challenge to all nuclear power-generatin...
Three martensitic candidate target materials, namely Alloys EP-823 and HT-9, and Type 422 stainless ...
Irradiation-assisted stress corrosion cracking is a costly degradation mechanism for austenitic stai...
During the use of nuclear reactors the properties of the structural materials change. Variations in ...