Development of ATR type steam separator performance analysis code and its validation, (1)
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center
Description
The purpose of the study is to develop a method for predicting steam carryunder which is one of the important characteristics of a steam separator. Bubbles returning to the liquid surface and trapped by the re-circulating flow are calculated by tracking the behavior of bubbles moving in liquid bulk where velocity and temperature distributions have been calculated before-hand in conjunction with the Monte-Carlo method. Regarding the statistics of bubbles, a survey of references and visual tests have been conducted. To validate this method, several tests to measure bubble behavior under air/water conditions at atmospheric pressure and high temperature and pressure ranging 3 ∼ 7 MPa have been conducted with a full-scale steam separator. As a result, the developed method predicted with good precision the carryunder ratio obtained by the full-scale tests under the condition that carried-under void fraction was less than 20 %, but underestimated carryunder ratio in the ATR 'Fugen' reactor in which steam drum water level was shallow and average void fraction in water bulk was high. This method has a characteristic that carryunder ratio is underestimated in the case that void fraction is more than 20 %. (author)
Additional details
Additional titles
- Subtitle (English)
- Carryunder characteristics
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 28
- Journal Issue
- 12
- Series
- J. Nucl. Sci. Technol. (Tokyo).
- Journal Page Range
- 1078-1089
- ISSN
- 0022-3131
- CODEN
- JNSTA
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 23083616
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AIR; BUBBLES; JATR REACTOR; MEDIUM PRESSURE; MONTE CARLO METHOD; PRESSURE DEPENDENCE; STEAM SEPARATORS; TEMPERATURE DEPENDENCE; TWO-PHASE FLOW; VERIFICATION; VOID FRACTION; WATER
- Descriptors DEC
- CALCULATION METHODS; EQUIPMENT; FLUID FLOW; FLUIDS; GASES; HEAVY WATER MODERATED REACTORS; HWLWR TYPE REACTORS; HYDROGEN COMPOUNDS; NATURAL URANIUM REACTORS; OXYGEN COMPOUNDS; PLUTONIUM REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SEPARATION EQUIPMENT; THERMAL REACTORS; VAPOR SEPARATORS; WATER COOLED REACTORS