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Title: Neutron Residual Stress Mapping for Spent Nuclear Fuel Storage Canister Weldment

Technical Report ·
DOI:https://doi.org/10.2172/1435212· OSTI ID:1435212
 [1];  [2];  [2];  [2]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science & Technology Division
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Neutron Scattering Division

Many radioactive materials within the nuclear fuel cycle present a significant hazard. Such materials include spent nuclear fuel, high-level waste, legacy waste and other nuclear materials that have no current outlet than storage. These materials are often held in long-term storage as an interim stage within their lifecycle. Lifecycles can include reuse or disposal. Safety and security of spent nuclear fuel (SNF) interim storage installations are very important, due to a great concentration of fission products, actinides and activation products. Stress corrosion cracking of interim storage containers has been identified as a high priority data gap by the Department of Energy. However, little has been done with regards to the canister weld material properties and their impact on stress corrosion, until recently from Sandia National Laboratory canister mockup program. Furthermore, because no post-weld heat treatment was required, the associated high tensile residual stress within these canister welds can drive the initiation and growth of stress corrosion cracking (SCC) cracks. In this work, we carried out in-situ neutron residual stress mapping on a weld plate sectioned from Sandia mock-up canister wall. Significant residual stress profiles were identified from the received longitudinal weld sample. The details of the weldment residual stress program development at ORNL are presented in this progress report. The generated residual stress profile from neutron diffraction technique is similar to that of Sandia residual stress data obtained from the deep hole drilling approach.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5)
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1435212
Report Number(s):
ORNL/TM-2018/827
Country of Publication:
United States
Language:
English