Analytical modeling of bwr safety relief valve blowdown phenomenon
Description
An analytical, qualitative understanding of the pool pressures measured during safety relief valve discharge in boiling water reactors equipped with X-quenchers has been developed and compared to experimental data. A pressure trace typically consists of a brief 25-35 Hz. oscillation followed by longer 5-15 Hz. oscillation. In order to explain the pressure response, a discharge line vent clearing model has been coupled with a Rayleigh bubble dynamic model. The local conditions inside the safety relief valve discharge lines and inside of the X-quencher were simulated successfully with RELAP5. The simulation allows one to associate the peak pressure inside the quencher arm with the onset of air discharge into the suppression pool. Using the pressure and thermodynamic quality at quencher exit of RELAP5 calculation as input, a Rayleigh model of pool bubble dynamics has successfully explained both the higher and lower frequency pressure oscillations. The higher frequency oscillations are characteristic of an air bubble emanating from a single row of quencher holes. The lower frequency pressure oscillations are characteristic of a larger air bubble containing all the air expelled from one side of an X-quencher arm
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- Imprint Title
- Proceedings of international nuclear power plant thermal hydraulics and operations topical meeting
- Journal Page Range
- p. B2-1-B2-8.
Conference
- Title
- International thermal hydraulics and plant operations topical meeting.
- Dates
- 22-24 Oct 1984.
- Place
- Taipei, TW (China).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17078705
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BLOWDOWN; BUBBLES; BWR TYPE REACTORS; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; OSCILLATIONS; PRESSURE MEASUREMENT; PRESSURE SUPPRESSION; REACTOR COOLING SYSTEMS; RELIEF VALVES; SYSTEMS ANALYSIS; TWO-PHASE FLOW
- Descriptors DEC
- CONTROL EQUIPMENT; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; FLUID FLOW; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; VALVES; WATER COOLED REACTORS; WATER MODERATED REACTORS