OECD MCCI Project: Category 2 Coolability Engineering Enhancement Tests (Final Report)
- Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division
Ex-vessel debris coolability is an important light water reactor (LWR) safety issue. For existing plants, resolution of this issue will confirm the technical basis for severe accident management guidelines (SAMGs). For new reactors, understanding this issue will help confirm the effectiveness of the design and implementation of new accident mitigation features and severe accident management design alternatives (SAMDAs). The first OECD-MCCI program conducted reactor material experiments focused on achieving the following technical objectives: i) provide confirmatory evidence and data for various cooling mechanisms through separate effect tests for severe accident model development, and ii) provide long-term 2-D coreconcrete interaction data for code assessment and improvement. On the basis of deliberations that spanned several Project Review Group (PRG) meetings, the MB subsequently approved the conduct of one large scale water-cooled basemat integral effect test to provide data on the cold-crucible method for melt stabilization, and two separate effect tests that utilized the SSWICS test facility to provide data on the melt fragmentation method for melt stabilization. This final report summarizes the test facilities, operating procedures, and key test results obtained from these three experiments. Additional details can be found in the test plans and follow-on data reports for the experiments.
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE; Nuclear Regulatory Commission (NRC); Organization for Economic Cooperation and Development (OECD) - Nuclear Energy Agency
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1177571
- Report Number(s):
- OECD/MCCI--2010-TR02; 114162
- Country of Publication:
- United States
- Language:
- English
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