Irradiation-assisted stress corrosion cracking (IASCC) is a significant materials issue for the light water reactor (LWR) industry and may also pose a problem for fusion power reactors that will use water as coolant. A new metallurgical process is proposed that involves the radiation-induced release into solution of minor impurity elements not usually thought to participate in IASCC. MnS-type precipitates, which contain most of the sulfur in stainless steels, are thought to be unstable under irradiation. First, Mn transmutes strongly to Fe in thermalized neutron spectra. Second, cascade-induced disordering and the inverse Kirkendall effect operating at the incoherent interfaces of MnS precipitates are thought to act as a pump to export Mn f...
Structural alloys for Generation-IV nuclear reactors need to endure a high neutron dose, high temper...
We have assessed the local solute redistribution at defect sinks in 20Cr–25Ni Nb-stabilised austeni...
We have assessed the local solute redistribution at defect sinks in 20Cr–25Ni Nb-stabilised austeni...
Although a number of candidate mechanisms have been proposed to participate in the IASCC phenomenon,...
Formation of a high density of Mn-Ni-Si nanoscale precipitates in irradiated reactor pressure vessel...
Irradiation-assisted stress corrosion cracking (IASCC) of several types of BWR field components fabr...
MasterIG (intergranular) cracking phenomena have been reassessed in heat resistant austenitic stainl...
To determine the effects of water chemistry on the susceptibility to irradiation-assisted stress cor...
Irradiation-assisted stress corrosion cracking is a costly degradation mechanism for austenitic stai...
The role of radiation-induced segregation (RIS) in irradiation-assisted stress corrosion cracking (I...
The role of radiation-induced segregation (RIS) in irradiation-assisted stress corrosion cracking (I...
Precipitation of various particles and their growth during rupture test have been investigated in TP...
A technique for studying the irradiation assisted stress corrosion (IASCC) behavior of proton irradi...
The overarching goal of this research is to advance understanding of, model and predict embrittlemen...
The overarching goal of this research is to advance understanding of, model and predict embrittlemen...
Structural alloys for Generation-IV nuclear reactors need to endure a high neutron dose, high temper...
We have assessed the local solute redistribution at defect sinks in 20Cr–25Ni Nb-stabilised austeni...
We have assessed the local solute redistribution at defect sinks in 20Cr–25Ni Nb-stabilised austeni...
Although a number of candidate mechanisms have been proposed to participate in the IASCC phenomenon,...
Formation of a high density of Mn-Ni-Si nanoscale precipitates in irradiated reactor pressure vessel...
Irradiation-assisted stress corrosion cracking (IASCC) of several types of BWR field components fabr...
MasterIG (intergranular) cracking phenomena have been reassessed in heat resistant austenitic stainl...
To determine the effects of water chemistry on the susceptibility to irradiation-assisted stress cor...
Irradiation-assisted stress corrosion cracking is a costly degradation mechanism for austenitic stai...
The role of radiation-induced segregation (RIS) in irradiation-assisted stress corrosion cracking (I...
The role of radiation-induced segregation (RIS) in irradiation-assisted stress corrosion cracking (I...
Precipitation of various particles and their growth during rupture test have been investigated in TP...
A technique for studying the irradiation assisted stress corrosion (IASCC) behavior of proton irradi...
The overarching goal of this research is to advance understanding of, model and predict embrittlemen...
The overarching goal of this research is to advance understanding of, model and predict embrittlemen...
Structural alloys for Generation-IV nuclear reactors need to endure a high neutron dose, high temper...
We have assessed the local solute redistribution at defect sinks in 20Cr–25Ni Nb-stabilised austeni...
We have assessed the local solute redistribution at defect sinks in 20Cr–25Ni Nb-stabilised austeni...