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Analysis of BCL transient ECC-bypass test with TRAC-PD2/MOD1 code. [PWR]

Conference ·
OSTI ID:5416668
;
As part of the independent assessment of the TRAC-PD2/MOD1 code, a calculation for the Battelle Columbus Laboratories (BCL) transient Emergency Core Cooling (ECC) bypass test was performed. The purpose of this calculation was to assess the code's capability to predict the lower plenum refill rate after the initiation of ECC water injection during a postulated large break LOCA in a PWR system. BCL conducted several ECC bypass tests in their 2/15th-scale model of a typical pressurized water reactor vessel.
Research Organization:
Brookhaven National Lab., Upton, NY (USA)
DOE Contract Number:
AC02-76CH00016
OSTI ID:
5416668
Report Number(s):
BNL-NUREG-30828; CONF-820609-21; ON: DE82009190
Country of Publication:
United States
Language:
English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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ACCIDENTS
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STRUCTURAL MODELS
WATER COOLED REACTORS
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