Pressurized thermal shock evaluation of the Calvert Cliffs Unit 1 Nuclear Power Plant

Technical Report · Sun Sep 01 04:00:00 EDT 1985

DOI:https://doi.org/10.2172/6051787· OSTI ID:6051787

Abbott, L ^[1]

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1. ed.

An evaluation of the risk to the Calvert Cliffs Unit 1 nuclear power plant due to pressurized thermal shock (PTS) has been completed by Oak Ridge National Laboratory (ORNL) with the assistance of several other organizations. This evaluation was part of a Nuclear Regulatory Commission program designed to study the PTS risk to three nuclear plants, the other two plants being Oconee Unit 1 and H.B. Robinson Unit 2. The specific objectives of the program were to (1) provide a best estimate of the frequency of a through-the-wall crack in the pressure vessel at each of the three plants, together with the uncertainty in the estimated frequency and its sensitivity to the variables used in the evaluation; (2) determine the dominant overcooling sequences contributing to the estimated frequency and the associated failures in the plant systems or in operator actions; and (3) evaluate the effectiveness of potential corrective measures.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6051787
• Report Number(s): NUREG/CR-4022; ORNL/TM-9408; ON: TI86004581
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCIDENTS
CALVERT CLIFFS-1 REACTOR
CONTAINERS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EVALUATION
FAILURES
FLUID MECHANICS
FRACTURE MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
OPERATION
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR VESSELS
REACTORS
RISK ASSESSMENT
THERMAL SHOCK
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS