Hot leg flow characteristics during two-phase natural circulation in pressurized water reactor
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
Description
The characteristics of two-phase flow in the hot legs of a PWR under off-normal conditions of two-phase natural circulation was studied experimentally using the ROSA-IV Large Scale Test Facility (LSTF). The LSTF is a 1/48 volumetrically-scaled simulator of a Westinghouse-type PWR. The cocurrent flow of steam and water through the hot legs formed a horizontally stratified two-phase flow during two-phase natural circulation. However, a flow regime transition to non-stratified flow occurred at the leg downstream end such that liquid could be pushed up by interfacial drag into the steam generator located above the hot leg. For relatively large two-phase natural circulation rates, this flow regime transition included a three-dimensional hydraulic jump since the hot leg flow was supercritical. (orig.)
Additional details
Publishing Information
- Publisher
- Braun.
- Imprint Place
- Karlsruhe (Germany, F.R.)
- ISBN
- 3-7650-1115-0
- Imprint Title
- Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 1
- Imprint Pagination
- 745 p.
- Journal Page Range
- p. 465-470.
Conference
- Title
- 4. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4).
- Dates
- 10-13 Oct 1989.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 22029458
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; HYDRAULICS; LOSS OF COOLANT; NATURAL CONVECTION; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR SAFETY EXPERIMENTS; TEST FACILITIES; TWO-PHASE FLOW; WESTINGHOUSE STANDARD REACTOR
- Descriptors DEC
- ACCIDENTS; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HEAT TRANSFER; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS