Steam-generator-tube-rupture transients for pressurized-water reactors

Conference · Fri Jan 01 00:00:00 EST 1982

OSTI ID:5047641

Dobranich, D; Henninger, R J; DeMuth, N S

Steam generator tube ruptures with and without concurrent main-steam-line break are investigated for pressurized water reactors supplied by the major US vendors. The goal of these analyses is to provide thermodynamic and flow conditions for the determination of iodine transport to the environment and to provide an evaluation of the adequacy of the plant safety systems and operating procedures for controlling these transients. The automatic safety systems of the plant were found to be adequate for the mitigation of these transients. Emergency injection system flows equilibrated with the leakage flows and prevented core uncovery. Sufficient time was afforded by the plant safety systems for the operators to identify the problem and to take appropriate measures.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5047641
• Report Number(s): LA-UR-82-2498; CONF-820802-20; ON: DE82021762
• Resource Relation: Conference: International meeting on thermal nuclear reactor safety, Chicago, IL, USA, 29 Aug 1982
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FISSION PRODUCT RELEASE
PWR TYPE REACTORS
STEAM GENERATORS
PRESSURE GRADIENTS
TUBES
FAILURES
RADIOACTIVE EFFLUENTS
RADIOACTIVITY TRANSPORT
REACTOR SAFETY
TRANSIENTS
BOILERS
MATERIALS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTORS
SAFETY
VAPOR GENERATORS
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220502 - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents