TY - GEN
T1 - Low temperature creep of used nuclear fuel during long term dry storage
AU - Beyer, Carl E.
AU - Tulenko, James S.
AU - Yang, Yong
AU - Fuchs, Gerhard E.
AU - Stubbins, James
AU - Eapen, Jacob
AU - Murty, Korukonda
PY - 2013
Y1 - 2013
N2 - The evaluation of the long term clad creep behavior of used nuclear fuel (UNF) in dry storage is being performed under the Integrated Research Project (ERP) "Fuel Aging in Storage and Transportation," (FAST) which includes six university partners with multiple investigators per university, as well as supporting advisors from Savanna River National Laboratory and Pacific Northwest National Laboratory. This effort is just in the beginning stages of its evaluation of data and model development, such that the results provided in this paper are of a preliminary nature. The evaluation of creep will characterize the low-temperature low-stress mechanisms relevant to dry storage. The major objectives are (1) to obtain data using highly oxidized/hydrided tubing under relevant stresses and temperatures, (2) to characterize and translate that data for development of a low temperature creep model input to FRAPCON and other codes to predict UNF behavior during dry storage, and (3) to formulate atomistic simulations to develop a better understanding of the long term creep behavior with emphasis on effects of oxygen and hydrogen as well as neutron irradiation in order to enable extrapolation of the models to long term storage.
AB - The evaluation of the long term clad creep behavior of used nuclear fuel (UNF) in dry storage is being performed under the Integrated Research Project (ERP) "Fuel Aging in Storage and Transportation," (FAST) which includes six university partners with multiple investigators per university, as well as supporting advisors from Savanna River National Laboratory and Pacific Northwest National Laboratory. This effort is just in the beginning stages of its evaluation of data and model development, such that the results provided in this paper are of a preliminary nature. The evaluation of creep will characterize the low-temperature low-stress mechanisms relevant to dry storage. The major objectives are (1) to obtain data using highly oxidized/hydrided tubing under relevant stresses and temperatures, (2) to characterize and translate that data for development of a low temperature creep model input to FRAPCON and other codes to predict UNF behavior during dry storage, and (3) to formulate atomistic simulations to develop a better understanding of the long term creep behavior with emphasis on effects of oxygen and hydrogen as well as neutron irradiation in order to enable extrapolation of the models to long term storage.
UR - http://www.scopus.com/inward/record.url?scp=84886899696&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=84886899696&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:84886899696
SN - 9781627486446
T3 - 14th International High-Level Radioactive Waste Management Conference, IHLRWMC 2013: Integrating Storage, Transportation, and Disposal
SP - 657
EP - 665
BT - 14th International High-Level Radioactive Waste Management Conference, IHLRWMC 2013
T2 - 14th International High-Level Radioactive Waste Management Conference: Integrating Storage, Transportation, and Disposal, IHLRWMC 2013
Y2 - 28 April 2013 through 2 May 2013
ER -