TRAC-PF1 analyses of potential pressurized-thermal-shock transients at a combustion-engineering PWR
Description
The study identified the importance of the initial plant conditions and loop flows to the PTS issue. If the plant was initially at hot-zero power (rather than full power), the same accident initiator could produce significantly lower downcomer temperatures because of the reduced decay heat and stored energy. Flow stagnation in all reactor coolant loops, which occurred in one transient, could lead to a vessel wall temperature that approached the relatively cold high-pressure-injection fluid temperature. However, routine operator actions would reduce the consequences of any of these simulated accidents if the pressure-temperature relationships prescribed in the operator guidelines are followed. ORNL will extend the results of the Los Alamos study by determining the probability of vessel failure and accident occurrence for an overall assessment of PTS risk. (orig./HP)
Additional details
Publishing Information
- Imprint Title
- 5th international meeting on thermal nuclear reactor safety. Proceedings. Vol. 1
- Imprint Pagination
- 761 p.
- Journal Page Range
- p. 320-329.
- Report number
- KFK--3880/1
Conference
- Title
- 5. international meeting on thermal nuclear reactor safety.
- Dates
- 9-13 Sep 1984.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 16068469
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; CRACKS; ECCS; FRACTURE MECHANICS; PRESSURE DEPENDENCE; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR VESSELS; RISK ASSESSMENT; THERMAL SHOCK; TRANSIENTS; WELDED JOINTS
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; JOINTS; MECHANICS; POWER REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS