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Title: The results of the CCI-3 reactor material experiment investigating 2-D core-concrete interaction and debris coolability with a silliceous concrete crucible.

Conference ·
OSTI ID:944026

The OECD-sponsored Melt Coolability and Concrete Interaction (MCCI) program is conducting reactor material experiments and associated analysis with the objectives of resolving the ex-vessel debris coolability issue, and to address remaining uncertainties related to long-term two-dimensional molten core-concrete interactions under both wet and dry cavity conditions. Achievement of these two objectives will demonstrate the efficacy of severe accident management guidelines for existing plants and provide the technical basis for better containment designs for future plants. Despite years of international research, there are remaining uncertainties in the models that evaluate the lateral vs. axial power split during core-concrete interaction because of a lack of truly two-dimensional experiment data. As a result, there are differences in the 2-D cavity erosion predicted by codes such as MELCOR, WECHSL, and COSACO. In the continuing effort to bridge this data gap, the third in a series of large scale Core-Concrete Interaction experiments (CCI-3) has been conducted as part of the MCCI program. This test involved the interaction of a 375 kg core-oxide melt within a two-dimensional siliceous concrete crucible. The initial phase of the test was conducted under dry conditions. After a predetermined ablation depth was reached, the cavity was flooded to obtain data on the coolability of a core melt after core-concrete interaction has progressed for some time. This paper provides a summary description of the test facility and an overview of test results.

Research Organization:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Organization:
FOR
DOE Contract Number:
DE-AC02-06CH11357
OSTI ID:
944026
Report Number(s):
ANL/NE/CP-117992; TRN: US0900498
Resource Relation:
Conference: 2006 International Congress on Advances in Nuclear Power Plants (ICAPP'06; Jun. 4, 2006 - Jun. 8, 2006; Reno, NV
Country of Publication:
United States
Language:
ENGLISH