AbstractIn this study we propose a rupture criterion for the creep crack growth in Zircaloy cladding on spent fuel in interim storage. Based on the creep fracture mechanics parameter, C∗, and the strain energy density criteria, the relationship between the creep crack growth rate and the fracture mechanics parameter, C∗, is established theoretically. The effects of hydride orientations, initial crack lengths and storage temperature profiles on cladding failure are discussed in detail. The results show that the initial crack length and the storage temperature profile play an important role in cladding failure during interim dry storage. We found that a higher storage temperature will cause a larger creep growth rate, leading to unstable crac...
The purpose of this analysis is to describe the condition of commercial Zircaloy clad fuel as it is ...
Post-irradiation studies on failure mechanisms of well characterized PWR rods were conducted for up ...
Hydrogen redistribution process in Zircaloy cladding of spent fuels was evaluated under the thermal ...
AbstractIn this study we propose a rupture criterion for the creep crack growth in Zircaloy cladding...
The licensing of interim dry storage of light-water reactor spent fuel requires assurance that relea...
Creep, a potential degradation mechanism of Zircaloy cladding after repository disposal of spent nuc...
Two potential degradation mechanisms, creep and stress corrosion cracking, of Zircaloy cladding duri...
A literature review and analysis were made of corrosion and degradation processes applicable to Zirc...
To investigate allowable peak cladding temperature and hoop stress for maintenance of cladding integ...
Zircaloy-4 is widely used in light water reactors (LWRs) for fuel cladding applications because of i...
Spent nuclear fuel claddings discharged from water reactors contain hydrogen up to 800 wppm dependin...
Safe interim dry storage of spent nuclear fuel (SNF) must be maintained for a minimum of twenty year...
The purpose of this study was to utilize a modified DATING code to evaluate the effects off normal t...
Interim dry storage of spent nuclear fuel (SNF) rods is of critical concern because a shortage of ex...
The Zircaloy cladding of water reactor fuel rods is susceptible to local breach-type failure, common...
The purpose of this analysis is to describe the condition of commercial Zircaloy clad fuel as it is ...
Post-irradiation studies on failure mechanisms of well characterized PWR rods were conducted for up ...
Hydrogen redistribution process in Zircaloy cladding of spent fuels was evaluated under the thermal ...
AbstractIn this study we propose a rupture criterion for the creep crack growth in Zircaloy cladding...
The licensing of interim dry storage of light-water reactor spent fuel requires assurance that relea...
Creep, a potential degradation mechanism of Zircaloy cladding after repository disposal of spent nuc...
Two potential degradation mechanisms, creep and stress corrosion cracking, of Zircaloy cladding duri...
A literature review and analysis were made of corrosion and degradation processes applicable to Zirc...
To investigate allowable peak cladding temperature and hoop stress for maintenance of cladding integ...
Zircaloy-4 is widely used in light water reactors (LWRs) for fuel cladding applications because of i...
Spent nuclear fuel claddings discharged from water reactors contain hydrogen up to 800 wppm dependin...
Safe interim dry storage of spent nuclear fuel (SNF) must be maintained for a minimum of twenty year...
The purpose of this study was to utilize a modified DATING code to evaluate the effects off normal t...
Interim dry storage of spent nuclear fuel (SNF) rods is of critical concern because a shortage of ex...
The Zircaloy cladding of water reactor fuel rods is susceptible to local breach-type failure, common...
The purpose of this analysis is to describe the condition of commercial Zircaloy clad fuel as it is ...
Post-irradiation studies on failure mechanisms of well characterized PWR rods were conducted for up ...
Hydrogen redistribution process in Zircaloy cladding of spent fuels was evaluated under the thermal ...