Integrity of PWR pressure vessels during overcooling accidents
The reactor pressure vessel in a pressurized water reactor is normally subjected to temperatures and pressures that preclude propagation of sharp, crack-like defects that might exist in the wall of the vessel. However, there is a class of postulated accidents, referred to as overcooling accidents, that can subject the pressure vessel to severe thermal shock while the pressure is substantial. As a result of such accidents, vessels containing high concentrations of copper and nickel, which enhance radiation embrittlement, may possess a potential for extensive propagation of preexistent inner surface flaws prior to the vessel's normal end of life. A state-of-the-art fracture-mechanics model was developed and has been used for conducting parametric analyses and for calculating several recorded PWR transients. Results of the latter analysis indicate that there may be some vessels that have a potential for failure in a few years if subjected to a Rancho Seco-type transient. However, the calculational model may be excessively conservative, and this possibility is under investigation.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6627313
- Report Number(s):
- CONF-821037-27; ON: DE83001936
- Resource Relation:
- Conference: 10. water reactor safety research information conference, Gaithersburg, MD, USA, 12 Oct 1982; Other Information: Portions of document are illegible
- Country of Publication:
- United States
- Language:
- English
Similar Records
Brief account of the effect of overcooling accidents on the integrity of PWR pressure vessels
Integrity of PWR pressure vessels during overcooling transients
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PRESSURE VESSELS
FRACTURE MECHANICS
THERMAL SHOCK
PWR TYPE REACTORS
REACTOR ACCIDENTS
THERMAL STRESSES
FAILURES
TRANSIENTS
ACCIDENTS
CONTAINERS
MECHANICS
REACTORS
STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled