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. For the purpose of evaluating this problem 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 today if subjected to a Rancho Seco (1978) or TMI-2 (1979) 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:
- 5091593
- Report Number(s):
- CONF-820802-12; ON: DE82020812
- Resource Relation:
- Conference: International meeting on thermal nuclear reactor safety, Chicago, IL, USA, 29 Aug 1982; Other Information: Portions of document are illegible
- Country of Publication:
- United States
- Language:
- English
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Brief account of the effect of overcooling accidents on the integrity of PWR pressure vessels
PWR pressure vessel integrity during overcooling accidents
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
PRESSURE VESSELS
FAILURES
THERMAL SHOCK
PWR TYPE REACTORS
STEELS
FRACTURE PROPERTIES
PHYSICAL RADIATION EFFECTS
CRACKS
STRESS ANALYSIS
ALLOYS
CONTAINERS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
RADIATION EFFECTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
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Light-Water Moderated
Nonboiling Water Cooled
360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties