Application of the APRIL computer code to the analysis of BWR core meltdown accidents
The APRIL code is a new computer code for the thermal-hydraulic analysis of severe accident sequences in boiling water reactors (BWRs), developed at Rensselaer Polytechnic Institute under the joint sponsorship of Empire State Electric Energy Research Corporation and Oak Ridge National Laboratory. The models developed for APRIL cover a broad spectrum of phenomena, including both the in-vessel and out-of-vessel thermal hydraulics. In particular, the modeling of heatup, degradation, and melting of individual BWR core materials and structures (fuel, cladding, canisters, and cruciform control rods) is based on an improved version of the model used in MELRPI. While the results of calculations for slow transients are almost independent of the core nodalization scheme, fast transients can be significantly affected by the node size. In particular, the above applies to zinc oxidation and hydrogen production.
- OSTI ID:
- 7100969
- Report Number(s):
- CONF-8711195-; TRN: 88-033354
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 55; Conference: American Nuclear Society winter meeting, Los Angeles, CA, USA, 15 Nov 1987
- Country of Publication:
- United States
- Language:
- English
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BWR TYPE REACTORS
REACTOR CORE DISRUPTION
REACTOR SAFETY
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A CODES
HEAT TRANSFER
HYDRAULICS
COMPUTERIZED SIMULATION
MELTDOWN
PRESSURE VESSELS
REACTOR ACCIDENTS
TWO-DIMENSIONAL CALCULATIONS
ACCIDENTS
COMPUTER CODES
CONTAINERS
ENERGY TRANSFER
FLUID MECHANICS
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