In-core melt progression for the MAAP 4 codes
- 1. Fauske and Associates, Inc., Burr Ridge, IL (United States)
Description
The MAAP 4 core melt progression model contains provisions for the formation of a molten debris pool surrounded by a crust during late phase core degradation. A predominantly oxidic molten pool with a predominantly metallic lower crust may naturally develop through a combination of models for real material phase diagrams, mechanistic relocation, and rules to recognize extremely low porosity and the liquid fractions of adjacent highly degraded nodes. Pool size and shape thus becomes relatively independent of core nodalization (which only governs the coarseness of the crust location). An upper pool crust is mechanistically allowed during consideration of radiative and convective heat losses from the pool top surface to surrounding core nodes, the core barrel, and upper internals. Circulation within the pool causes mass and energy exchange between participating pool nodes, and determines the heat fluxes to the boundary crusts. Side and bottom node failure is predicted based on the time, temperature, and stress. Calculations demonstrate that this concept allows simulation of the degraded core geometry observed during the TMI-2 accident. (author)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 1
- Imprint Pagination
- 772 p.
- Journal Page Range
- p. 10F1-10F7
- Report number
- INIS-XA-N--080
Conference
- Title
- 4. international topical meeting on nuclear thermal hydraulics, operations and safety
- Dates
- 5-8 Apr 1994
- Place
- Taipei, Taiwan (China)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35095503
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ENERGY TRANSFER; HEAT FLUX; HEAT LOSSES; M CODES; MELTDOWN; NODAL EXPANSION METHOD; RADIATIVE COOLING; REACTOR CORES
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; COMPUTER CODES; COOLING; ENERGY LOSSES; ENERGY TRANSFER; HEAT TRANSFER; LOSSES; REACTOR ACCIDENTS; REACTOR COMPONENTS
Optional Information
- Notes
- 9 refs, 9 figs, 1 tab