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Title: Code for predicting the temperature and oxidation of undercooled cores

Technical Report ·
OSTI ID:5534656

This report documents the status of a computer code developed by Argonne National Laboratory (ANL) and the Nuclear Safety Analysis Center (NSAC) for predicting temperatures and oxidation of a pressurized-water reactor (open lattice) core during an undercooling transient. The initial use of this code has been for analyzing the TMI-2 core initial uncovery and core heat up during the accident of March, 1979. In the initial investigations of the TMI-2 accident, it was concluded that the first major core damage occurred during the first period of complete loss of forced coolant circulation in the core (100 to 174 minutes after turbine trip). The ANL/NSAC core heatup code was originally created to focus on the TMI-2 core during this uncovery period. This focus greatly simplifies the modeling and computational needs through elimination, as either irrelevant or unresolvable, of specific models for the balance of the primary loop and the secondary loop.

Research Organization:
Argonne National Lab., IL (USA)
DOE Contract Number:
W-31-109-ENG-38
OSTI ID:
5534656
Report Number(s):
EPRI-NSAC-11; ON: DE82004493; TRN: 82-006613
Country of Publication:
United States
Language:
English