Quality assurance of PTS thermal hydraulic calculations at BNL. [Pressurized Thermal Shock]

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:5376317

Rohatgi, U S; Pu, J; Jo, J; Saha, P

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
• Resource Relation: Conference: 11. NRC water reactor safety research information meeting, Gaithersburg, MD, USA, 14 Oct 1983
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
OCONEE-1 REACTOR
THERMAL SHOCK
COOLING
LOSS OF COOLANT
POWER-COOLING-MISMATCH ACCIDENTS
PRESSURE VESSELS
ACCIDENTS
CONTAINERS
ENRICHED URANIUM REACTORS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled