TY - GEN
T1 - PRA-Radial hydride embrittlement in spent PWR nuclear fuel cladding
AU - Eidelpes, E.
AU - Ibarra, L. F.
AU - Medina, R. A.
N1 - Funding Information:
This material is based upon work supported under a Department of Energy Nuclear Energy University Programs. Any opinions, findings, conclusions or recommendations expressed in this publication are those of the authors and do not necessarily reflect the views of the Department of Energy Office of Nuclear Energy.
PY - 2017
Y1 - 2017
N2 - The work presented in this paper is part of investigations on the structural integrity of Spent Nuclear Fuel (SNF) casks after long-term storage and subjected to normal or accidental conditions of transport. The main challenge of this assessment is to account for the time dependent material degradation mechanisms of the cask components. A Probabilistic Risk Assessment (PRA) is used for the overall assessment of the structural integrity of the relevant package components. SNF rod cladding is likely to control structural failure due to mechanical loads, which can be accelerated by hydride related material degradation of fuel rods after long-term storage. Due to limited available experimental data, statistical methods are used to predict the fuel rod conditions between beginning of storage and moment of transport. The value of the Rod Internal Pressure (RIP) appears to be a driving force for the hydride-induced embrittlement. RIP examination data and recent simulations point towards relatively low Cladding Hoop Stresses (CHSs) in standard rods during drying procedures. An exemplary PRA of the likelihood of cladding embrittlement due to Radial Hydride Reorientation (RHR) is presented. The preliminary model indicates a relatively low probability of cladding embrittlement for standard fuel rods.
AB - The work presented in this paper is part of investigations on the structural integrity of Spent Nuclear Fuel (SNF) casks after long-term storage and subjected to normal or accidental conditions of transport. The main challenge of this assessment is to account for the time dependent material degradation mechanisms of the cask components. A Probabilistic Risk Assessment (PRA) is used for the overall assessment of the structural integrity of the relevant package components. SNF rod cladding is likely to control structural failure due to mechanical loads, which can be accelerated by hydride related material degradation of fuel rods after long-term storage. Due to limited available experimental data, statistical methods are used to predict the fuel rod conditions between beginning of storage and moment of transport. The value of the Rod Internal Pressure (RIP) appears to be a driving force for the hydride-induced embrittlement. RIP examination data and recent simulations point towards relatively low Cladding Hoop Stresses (CHSs) in standard rods during drying procedures. An exemplary PRA of the likelihood of cladding embrittlement due to Radial Hydride Reorientation (RHR) is presented. The preliminary model indicates a relatively low probability of cladding embrittlement for standard fuel rods.
UR - https://www.scopus.com/pages/publications/85040195941
M3 - Conference contribution
AN - SCOPUS:85040195941
T3 - ANS IHLRWM 2017 - 16th International High-Level Radioactive Waste Management Conference: Creating a Safe and Secure Energy Future for Generations to Come - Driving Toward Long-Term Storage and Disposal
SP - 195
EP - 205
BT - ANS IHLRWM 2017 - 16th International High-Level Radioactive Waste Management Conference
PB - American Nuclear Society
T2 - 16th International High-Level Radioactive Waste Management Conference: Creating a Safe and Secure Energy Future for Generations to Come - Driving Toward Long-Term Storage and Disposal, IHLRWM 2017
Y2 - 9 April 2017 through 13 April 2017
ER -