ACE program Phases C and D: Molten corium concrete interaction (MCCI) experiments and corium melt coolability experiments (MACE)
- 1. Electric Power Research Inst., Palo Alto, CA (United States)
- 2. Argonne National Lab., IL (United States)
Description
A series of experiments are being performed at Argonne National Laboratory (ANL) investigating the interaction of molten core material with concrete and its coolability with water. The work is supported by the ACE (Advanced Containment Experiments) International Consortium. This consortium consists of 19 countries; with the US participation shared by Nuclear Regulatory Commission (NRC), Department of Energy (DOE), Electric Power Research Institute (EPRI) and Westinghouse. The project is managed by EPRI. The general objectives of the molten core concrete interaction (MCCI) experiments are to measure: (1) the releases of refractory fission product species, i.e., oxides of lanthanum, barium, cesium and strontium; (2) the physical and chemical character of the aerosols generated; and (3) the thermal-hydraulic aspects of the interaction, including the concrete ablation rate. The principal objectives of the melt attack and coolability experiments (MACE) project are to: (1) obtain data on coolability with water of corium melt interacting with basemat concrete; and (2) develop models for insertion in the industry and NRC-sponsored codes
Files
Additional details
Publishing Information
- Imprint Title
- Transactions of the nineteenth water reactor safety information meeting
- Imprint Pagination
- 220 p.
- Journal Page Range
- p. 13.7-13.8.
- Report number
- NUREG/CP--0118
Conference
- Title
- 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
- Dates
- 28-30 Oct 1991.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059473
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANL; BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; CONCRETES; COOLING; COORDINATED RESEARCH PROGRAMS; CORIUM; EPRI; FISSION PRODUCTS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MELTDOWN; OXIDATION; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; STAINLESS STEELS; US DOE; US NRC; ZIRCONIUM
- Descriptors DEC
- ACCIDENTS; ALLOYS; BUILDING MATERIALS; CARBON ADDITIONS; CHEMICAL REACTIONS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; ISOTOPES; MATERIALS; METALS; NATIONAL ORGANIZATIONS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTORS; RESEARCH PROGRAMS; SAFETY; SIMULATION; STEELS; THERMAL REACTORS; TRANSITION ELEMENTS; US AEC; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911079--.