The work reported here is an investigation of the sensitivity of component temperatures of a storage system, including fuel cladding temperatures, in response to age-related changes that could degrade the design-basis thermal behavior of the system. Three specific areas of interest were identified for this study. • degradation of the canister backfill gas from pure helium to a mixture of air and helium, resulting from postulated leakage due to stress corrosion cracking (SCC) of canister welds • changes in surface emissivity of system components, resulting from corrosion or other aging mechanisms, which could cause potentially significant changes in temperatures and temperature distributions, due to the effect on thermal radiation exchange b...
The evolution during storage of properties relevant for safe handling/processing of high specific al...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
To investigate allowable peak cladding temperature and hoop stress for maintenance of cladding integ...
Loading requirements for dry cask storage of spent nuclear fuel are driven primarily by decay heat c...
Ageing processes occurring during storage of spent nuclear fuel rods are safety-relevant both for st...
Dry cask safety analyses and material degradation studies depend on reliable best- estimate thermal ...
The Los Alamos National Laboratory's Nuclear Materials Storage Facility (NMSF) is being renovated fo...
The safety assessment of spent nuclear fuel (SNF) during storage/disposal requires defining/extrapol...
The nuclear fuel assemblies are used in the reactor for 3 to 6 years, and then are stored underwater...
The purpose of this study was to utilize a modified DATING code to evaluate the effects off normal t...
Spent nuclear fuel is very inhomogeneous and complex material. Its dissulution behaviour is affected...
International audienceA two-dimensional computational model of a loaded used nuclear fuel canister f...
The licensing of spent fuel storage casks is generally based on conservative analyses that assume a ...
Spent fuel transportation and storage cask designs based on a burnup credit approach must consider i...
There is an increasing need in the United States and around the world to move used nuclear fuel from...
The evolution during storage of properties relevant for safe handling/processing of high specific al...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
To investigate allowable peak cladding temperature and hoop stress for maintenance of cladding integ...
Loading requirements for dry cask storage of spent nuclear fuel are driven primarily by decay heat c...
Ageing processes occurring during storage of spent nuclear fuel rods are safety-relevant both for st...
Dry cask safety analyses and material degradation studies depend on reliable best- estimate thermal ...
The Los Alamos National Laboratory's Nuclear Materials Storage Facility (NMSF) is being renovated fo...
The safety assessment of spent nuclear fuel (SNF) during storage/disposal requires defining/extrapol...
The nuclear fuel assemblies are used in the reactor for 3 to 6 years, and then are stored underwater...
The purpose of this study was to utilize a modified DATING code to evaluate the effects off normal t...
Spent nuclear fuel is very inhomogeneous and complex material. Its dissulution behaviour is affected...
International audienceA two-dimensional computational model of a loaded used nuclear fuel canister f...
The licensing of spent fuel storage casks is generally based on conservative analyses that assume a ...
Spent fuel transportation and storage cask designs based on a burnup credit approach must consider i...
There is an increasing need in the United States and around the world to move used nuclear fuel from...
The evolution during storage of properties relevant for safe handling/processing of high specific al...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
To investigate allowable peak cladding temperature and hoop stress for maintenance of cladding integ...