Reflooding Experiment on BETA Test Loop: The Effects of Inlet Temperature on the Rewetting Velocity
- 1. Centre for Development of Nuclear Safety Technology, National Nuclear Energy Agency, Serpong (Indonesia)
Description
Loss of Coolant Accident (LOCA) on Nuclear Reactor Plant is an important topic because this condition is a severe accident that can be postulated. The phenomenon of LOCA on Pressurized Water Reactor (PWR) can be divided in three stages, e.g.: blowdown, refill and reflood. In the view of Emergency Coolant System evaluation, the reflood is the most important stage. In this stage, an injection of emergency water coolant must be done in a way that the core can be flooded and the overheating can be avoid. The experiment of rewetting on BETA Test Loop had been conducted. The experiment using one heated rod of the test section to study effects of inlet temperature on the wetting velocity. Results of the series of experiments on 2,5 lt/min flow rate and variable of temperature : 28 oC, 38 oC, 50 oC, 58 oC it was noticed that for 58 oC inlet temperature of test section and 572 oC rod temperature the rewetting phenomenon has been observed. The time of refill was 32.81 sec and time of rewetting was 42.87 sec. (author)
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44011594.pdf
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Additional details
Additional titles
- Original title (Indonesian)
- Eksperimen Reflooding pada Untai BETA: Pengaruh Temperatur Masukan pada Kecepatan Pembahasan
Publishing Information
- Publisher
- National Nuclear Energy Agency
- Imprint Place
- Serpong (Indonesia)
- Imprint Title
- Proceeding of the Eighth Scientific Presentation on Nuclear Safety Technology
- Imprint Pagination
- 278 p.
- Journal Page Range
- p. 139-148
- ISSN
- 1410-0533
- Report number
- INIS-ID--049
Conference
- Title
- 8. Scientific Presentation on Nuclear Safety Technology
- Original Conference Title
- Presentasi Ilmiah Teknologi Keselamatan Nuklir VIII
- Dates
- 26-27 Feb 2003
- Place
- Serpong (Indonesia)
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 44011594
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLANTS; FLOW RATE; HEATING; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR ACCIDENTS; REWETTING; ROD EJECTION ACCIDENTS; SAFETY ANALYSIS; SCRAM; TEMPERATURE CONTROL; THERMAL HYDRAULICS; WATER
- Descriptors DEC
- ACCIDENTS; CONTROL; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR SHUTDOWN; REACTORS; SHUTDOWN; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 6 refs.; 10 figs. Imprint:Prosiding Presentasi Ilmiah Teknologi Keselamatan Nuklir VIII