The purpose of this study was to utilize a modified DATING code to evaluate the effects off normal temperature conditions occurring during dry storage would have on allowable storage limits for Zircaloy cladding. Towards this, Zircaloy creep tubes were used to perform creep studies in a temperature range of 300-500⁰C with an applied stress range of 40-65 MPa. This allowed for the development of updated creep rate equations with the forms utilized in past studies by Mayuzumi and Matsuo to be fit. These fit equations along with the original mechanistic creep equations from the DATING code were used to evaluate the effects of off normal temperature events ranging from 10-100⁰C beginning at points in the fuels lifetime ranging from 5%-75% of ...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
The work reported here is an investigation of the sensitivity of component temperatures of a storage...
There is an increasing need in the United States and around the world to move used nuclear fuel from...
The purpose of this study was to utilize a modified DATING code to evaluate the effects off normal t...
Creep, a potential degradation mechanism of Zircaloy cladding after repository disposal of spent nuc...
Interim dry storage of spent nuclear fuel (SNF) rods is of critical concern because a shortage of ex...
Safe interim dry storage of spent nuclear fuel (SNF) must be maintained for a minimum of twenty year...
Safe interim dry storage of spent nuclear fuel (SNF) must be maintained for a minimum of twenty year...
Two potential degradation mechanisms, creep and stress corrosion cracking, of Zircaloy cladding duri...
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...
Zircaloy-4 is widely used in light water reactors (LWRs) for fuel cladding applications because of i...
To investigate allowable peak cladding temperature and hoop stress for maintenance of cladding integ...
Ageing processes occurring during storage of spent nuclear fuel rods are safety-relevant both for st...
The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial rea...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
The work reported here is an investigation of the sensitivity of component temperatures of a storage...
There is an increasing need in the United States and around the world to move used nuclear fuel from...
The purpose of this study was to utilize a modified DATING code to evaluate the effects off normal t...
Creep, a potential degradation mechanism of Zircaloy cladding after repository disposal of spent nuc...
Interim dry storage of spent nuclear fuel (SNF) rods is of critical concern because a shortage of ex...
Safe interim dry storage of spent nuclear fuel (SNF) must be maintained for a minimum of twenty year...
Safe interim dry storage of spent nuclear fuel (SNF) must be maintained for a minimum of twenty year...
Two potential degradation mechanisms, creep and stress corrosion cracking, of Zircaloy cladding duri...
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...
Zircaloy-4 is widely used in light water reactors (LWRs) for fuel cladding applications because of i...
To investigate allowable peak cladding temperature and hoop stress for maintenance of cladding integ...
Ageing processes occurring during storage of spent nuclear fuel rods are safety-relevant both for st...
The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial rea...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
The work reported here is an investigation of the sensitivity of component temperatures of a storage...
There is an increasing need in the United States and around the world to move used nuclear fuel from...