skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: OECD MCCI Project: 2-D Core Concrete Interaction (CCI) Tests. CCI-4 Quick Look Data Report (Final, Rev. 0)

Technical Report ·
DOI:https://doi.org/10.2172/1177586· OSTI ID:1177586
 [1];  [1];  [1];  [1]
  1. 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 for various cooling mechanisms through separate effect tests and data for severe accident code model development, and ii) provide longer-term two-dimensional core-concrete interaction data for code assessment and improvement. The fourth test that is addressed in this report, CCI-4, utilized a similar test apparatus and experiment boundary conditions, including a limestone/common sand concrete test section. However, instead of a fully oxidized PWR melt, CCI-4 utilized a partially oxidized BWR core melt containing ~ 8 wt % structural steel constituents. Thus, this test evaluated the effect of elevated melt metal content on two-dimensional cavity erosion and debris cooling behavior. The experiment was conducted on May 26, 2007. The objective of this quick look data report is to provide early thermalhydraulic results from this test so that the PRG will have sufficient information to begin formulating recommendations for the next experiment to be conducted in this test category. To this end, a summary description of the test apparatus is provided first, followed by descriptions of the test operating procedure and key experiment results. Overall specifications for CCI-4 are provided. A full length data report that includes the results of posttest examinations will be provided when that phase of the work is completed.

Research Organization:
Argonne National Lab. (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:
1177586
Report Number(s):
OECD/MCCI-2007-TR04; 114414
Country of Publication:
United States
Language:
English