Quality assurance of PTS thermal hydraulic calculations at BNL. [Pressurized Thermal Shock]
Rapid cooling of the reactor pressure vessel at high pressure has a potential of challenging the vessel integrity. This phenomenon is called overcooling or Pressurized Thermal Shock (PTS). The Nuclear Regulatory Commission (NRC) has selected three plants representing three types of PWRs in use for detailed PTS study. Oconee-1 (B and W), Calvert Cliffs (C.E.), and H.B. Robinson (Westinghouse). The Brookhaven National Laboratory (BNL) has been requested by NRC to review and compare the input decks developed at LANL and INEL, and to compare and explain the differences between the common calculations performed at these two laboratories. However, for the transients that will be computed by only one laboratory, a consistency check will be performed. So far only Oconee-1 calculations have been reviewed at BNL, and the results are presented here.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5376317
- Report Number(s):
- BNL-NUREG-33988; CONF-8310143-73; ON: DE84004189
- Country of Publication:
- United States
- Language:
- English
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Preliminary development of an integrated approach to the evaluation of pressurized thermal shock as applied to the Oconee Unit 1 Nuclear Power Plant
Review of thermal-hydraulic calculations for Calvert Cliffs and H. B. Robinson PTS study. [Pressurized thermal shock]
Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CONTAINERS
COOLING
ENRICHED URANIUM REACTORS
LOSS OF COOLANT
OCONEE-1 REACTOR
POWER REACTORS
POWER-COOLING-MISMATCH ACCIDENTS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
THERMAL SHOCK
WATER COOLED REACTORS
WATER MODERATED REACTORS