PTSE-2: HSST pressurized thermal shock experiment with low upper-shelf energy toughness material
- 1. Oak Ridge National Lab., TN
Description
The second pressurized thermal shock experiment (PTSE-2) of the Heavy-Section Steel Technology Program was conceived to investigate fracture behavior of steel with low ductile-tearing resistance. In overcooling accidents, damage by fracture is potentially a problem of serious concern only in instances of vessel materials that have high transition temperatures and low Charpy impact energies at upper-shelf temperatures. In some cases the outcome of an overcooling accident analysis is principally determined by the transition temperature of the material and its influence on the initiation of brittle fracture; in such cases, low tearing resistance concomitant with low impact energy may be unimportant. If, however, crack arrest is also a contributing factor, then ductile tearing should also be considered. An arrested cleavage crack may be unstable with respect to ductile tearing. PTSE-2 is designed to produce a cleavage arrest under conditions that will immediately induce unstable tearing. The flawed material in the test vessel was fabricated to have low toughness at Charpy upper-shelf temperatures. It is the principal objective of this test to elucidate this fracture process. A secondary objective of PTSE-2 is to extend the investigation of warm prestressing that was started in the first pressurized thermal shock experiment
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission fourteenth water reactor safety information meeting. Volume 2. Research in nondestructive evaluation, environmental effects in primary system components, pressure vessel research, irradiation effects on RPV steels, degraded piping research
- Journal Page Range
- p. 287-298.
- Report number
- NUREG/CP--0082-Vol.2
Conference
- Title
- 14. water reactor safety information meeting.
- Dates
- 27-31 Oct 1986.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19002094
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CRACK PROPAGATION; DUCTILE-BRITTLE TRANSITIONS; FRACTURE MECHANICS; LOSS OF COOLANT; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR SAFETY; THERMAL SHOCK; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ENRICHED URANIUM REACTORS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS