TRAC analyses of multiple-failure steam generator tube rupture events in pressurized water reactors

Conference · Thu Jan 01 00:00:00 EST 1987 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5580242

Nassersharif, B

Steam generator tube rupture (SGTR) transients recently have received attention because of their frequency of occurrence and severity. Previous studies have assessed the consequences of SGTR incidents both with and without a concurrent mainstream-line break and with the parametric study of the assumption of the simultaneous rupture of one, five, or ten tubes. The studies were performed for three generic types of US pressurized water reactors (PWRs) and were conducted with the assumption of a generic operating strategy (e.g., the same procedure for all cases studied) to control the consequences of the transient. Those studies allowed an assessment of the severity of the transient for various numbers of tube breaks and a comparison of the response of each of the plant types because the same scenario was used as a basis of simulation for each plant. An important conclusion of the previous study was that the calculated total mass transferred to the environment was as much or more for the case of one SGTR as it was for ten SGTRs. In the present study, the authors concentrate on the more probable case of a single tube failure, although multiple once-through SG (OTSG) failures in both loops were also considered for the Babcock and Wilcox (B and W) SGs.

• Research Organization: Texas A and M, College Station
• OSTI ID: 5580242
• Report Number(s): CONF-870837-; TRN: 88-009799
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 54; Conference: 13. American Nuclear Society international meeting on nuclear power plant operation, Chicago, IL, USA, 30 Aug 1987
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
STEAM GENERATORS
TUBES
RUPTURES
FAILURES
HEAT TRANSFER
HYDRAULICS
PRIMARY COOLANT CIRCUITS
REACTOR OPERATORS
TRANSIENTS
US NRC
VALVES
BOILERS
CONTROL EQUIPMENT
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EQUIPMENT
FLOW REGULATORS
FLUID MECHANICS
MECHANICS
NATIONAL ORGANIZATIONS
PERSONNEL
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
US ORGANIZATIONS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled