Improvements in CORCON heat transfer modeling
Conference
·
OSTI ID:5342317
The CORCON computer code was developed at Sandia National Laboratories in order to model ex-vessel core debris - concrete interactions. Early comparisons between experimental data and CORCON calculations indicated that the existing melt-concrete heat transfer models were inadequate. An improved melt-concrete heat transfer model has been developed that consists of the Kutateladze nucleate boiling correlation acting in series with a melted slag film. Comparison of experiment results to calculations made using this model indicate good to excellent agreement for the TURC, SWISS and BETA tests that have been conducted at SNL and KfK.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5342317
- Report Number(s):
- SAND-86-1883C; CONF-8609126-2; ON: TI86015399
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BUILDING MATERIALS
C CODES
COMPUTER CODES
COMPUTERIZED SIMULATION
CONCRETES
CORIUM
ENERGY TRANSFER
HEAT TRANSFER
MATERIALS
MELTDOWN
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTORS
SIMULATION
THERMAL POWER PLANTS
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BUILDING MATERIALS
C CODES
COMPUTER CODES
COMPUTERIZED SIMULATION
CONCRETES
CORIUM
ENERGY TRANSFER
HEAT TRANSFER
MATERIALS
MELTDOWN
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTORS
SIMULATION
THERMAL POWER PLANTS