Reflooding heat transfer in zirconium alloy rod bundle of VVER reactor
- 1. Moscow Power Engineering Inst. (USSR)
Description
An experimental study has been conducted to investigate the heat transfer process in reflooding in seven rod bundles of Zr+1%Nb alloy with water injection from the bottom only, from the top only and from both. The results of the experimental research are several empirical correlation for (i) rewetting velocity, (ii) heat transfer coefficient downstream of the quench front and, (iii) heat transfer enhancement due to grid spacers for the bottom reflooding condition. Comparing the bottom and the top reflooding conditions, it is found that the first case is preferable because the heater rod peak temperature is 100 K lower and the full rewetting time is three times less than for the second case. Flow regimes in bundles differ from those in tubes. The inverted annular flow boiling regime in the rod bundles is very short and changes to dispersed flow film boiling rapidly. (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. 584-590.
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
- 22029467
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORE FLOODING SYSTEMS; FILM BOILING; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; LOSS OF COOLANT; REACTOR SAFETY EXPERIMENTS; REWETTING; WWER TYPE REACTORS; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALLOYS; BOILING; ECCS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; PHASE TRANSFORMATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS