COMPASS - New modeling and simulation approach to PWR in-vessel accident progression
- 1. Rensselaer Polytechnic Institute, Troy (United States)
- 2. Podowski Engineering Consulting, Clifton Park (United States)
- 3. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The objective of this paper is to discuss the modeling principles of phenomena governing core degradation/melting and in-vessel melt relocation during severe accidents in light water reactors. The proposed modeling approach has been applied in the development of a new accident simulation package, COMPASS (COre Meltdown Progression Accident Simulation Software). COMPASS can be used either as a stand-alone tool to simulate in-vessel meltdown progression up to and including RPV failure, or as a component of an integrated simulation package being developed in Korea for the APR1400 reactor. Interestingly, since the emphasis in the development of COMPASS modeling framework has been on capturing generic mechanistic aspects of accident progression in light water reactors, several parts of the overall model should be useful for future accident studies of other reactor designs, both PWRs and BWRs. The issues discussed in the paper include the overall structure of the model, the rationale behind the formulation of the governing equations and the associated simplifying assumptions, as well as the methodology used to verify both the physical and numerical consistencies of the overall solver. Furthermore, the results of COMPASS validation against two experimental data sets (CORA and PHEBUS) are shown, as well as of the predicted accident progression at TMI-2 reactor.
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Technology
- Journal Volume
- 51
- Journal Issue
- 8
- Series
- 15 refs, 16 figs
- Journal Page Range
- p. 1916-1938
- ISSN
- 1738-5733
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 51108570
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; C CODES; COMPASS DETECTOR; EXPERIMENTAL DATA; MELTDOWN; MELTING; PWR TYPE REACTORS; REACTOR DESIGN; SIMULATION
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; COMPUTER CODES; DATA; DESIGN; ENRICHED URANIUM REACTORS; INFORMATION; MEASURING INSTRUMENTS; NUMERICAL DATA; PHASE TRANSFORMATIONS; POWER REACTORS; RADIATION DETECTORS; REACTOR ACCIDENTS; REACTOR LIFE CYCLE; REACTORS; SEVERE ACCIDENTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS