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Collaborative Study on Weldability of Irradiated Stainless Steel 304 Materials Removed from The NRU Reactor

Technical Report ·
DOI:https://doi.org/10.2172/1968686· OSTI ID:1968686
 [1];  [1];  [1];  [1];  [2];  [2];  [3];  [3]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
  2. Canadian Nuclear Laboratories, Chalk River, ON (Canada)
  3. Electric Power Research Inst. (EPRI), Knoxville, TN (United States)
+ Show Author Affiliations
A collaborative research on developing advanced welding technologies for irradiated stainless steel 304 materials between CNL and ORNL has been established to support both U.S. and Canadian interests in evaluation of weld repair techniques on irradiated materials to support continuous operation of commercial nuclear power. The work utilizes unique material from the National Research Universal (NRU) reactor and the specialized welding hot cell facility at ORNL. The objective is to explore suitable welding technique and parameters and to determine the helium concentration limitation in terms of irradiated stainless-steel weldability. An additional objective is to develop the knowledge and understanding of cracking mechanisms induced by high concentration of helium in the process of weld repair of the irradiated structural alloys. This report summarizes the experimental welding evaluation on irradiated material from the NRU reactor containing helium concentrations ranging from 12 to 45 atomic parts per million (appm).
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1968686
Report Number(s):
ORNL/TM--2023/2832; CRADA No. NFE-19-07912
Country of Publication:
United States
Language:
English

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36 MATERIALS SCIENCE