Experimental investigation of the coolability of blocked hexagonal bundles
Description
Highlights: • Experiments were performed with electrically heated hexagonal fuel bundles. • Coolability of ballooned VVER-440 type bundle was confirmed up to high blockage rate. • Pellet relocation effect causes delay in the cool-down of the bundle. • The bypass line does not prevent the reflood of ballooned fuel rods. - Abstract: The CODEX-COOL experimental series was carried out in order to evaluate the effect of ballooning and pellet relocation in hexagonal bundles on the coolability of fuel rods after a LOCA event. The effects of blockage geometry, coolant flowrate, initial temperature and axial profile were investigated. The experimental results confirmed that a VVER bundle up to 80% blockage rate remains coolable after a LOCA event under design basis conditions. The ballooned section creates some obstacles for the cooling water during reflood of the bundle, but this effect causes only a short delay in the cooling down of the hot fuel rods. The accumulation of fuel pellet debris in the ballooned volume results in a local power peak, which leads to further slowing down of quench front.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2017.03.030Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2017.03.030;
- PII
- S0029-5493(17)30142-5;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 317
- Journal Page Range
- p. 51-58
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48062652
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- COOLING; CORIUM; EXPERIMENT RESULTS; FLOW RATE; FUEL ELEMENT CLUSTERS; FUEL PELLETS; FUEL RODS; LOSS OF COOLANT; SWELLING; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; DEFORMATION; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUEL ELEMENTS; PELLETS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.