Simulation of Phases 3 and 4 of the TMI-2 accident using MAAP-DOE and MAAP 3. 0B, Task 3. 9
- Fauske and Associates, Inc., Burr Ridge, IL (USA)
- Argonne National Lab., IL (USA)
Phases 3 and 4 of the TMI-2 accident have been simulated using both MAAP 3.0B and the enhanced MAAP code version developed for the US Department of Energy (DOE). Predictions based on MAAP 3.0B are only fair, since the MAAP 3.0B version of the code does not model degraded core recovery. Predictions with the DOE enhanced version of MAAP are successful for Phase 3 of the accident, but not as successful for Phase 4. Primary system pressure and hydrogen generation, as predicted by the DOE code version for Phase 3, are in agreement with plant data and best estimate analyses. Code results indicate that the relocation at 224 times could not have occurred, in contrast to the actual plant end state. Results for core temperature and pressurizer level indicate that heat transfer from the core, and therefore the steaming rate from the vessel, may have been overestimated during Phase 4 of the accident. For Phase 4, these factors contribute to the disagreement between code predictions for pressurizer level and primary system pressure, and plant data. 22 refs., 34 figs., 5 tabs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC07-76ID01570; W-31109-ENG-38
- OSTI ID:
- 6991532
- Report Number(s):
- DOE/ID-10259; MISC--89132; ON: DE90013097
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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99 GENERAL AND MISCELLANEOUS
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ACCIDENTS
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ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
M CODES
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PRESSURIZERS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
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SIMULATION
TEMPERATURE DISTRIBUTION
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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99 GENERAL AND MISCELLANEOUS
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ACCIDENTS
COMPUTER CODES
COMPUTERIZED SIMULATION
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HEAT TRANSFER
HYDRAULICS
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POWER REACTORS
PRESSURIZERS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
TEMPERATURE DISTRIBUTION
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS