3-D numerical investigation of water/CuO nanofluid critical heat flux phenomenon in a PWR core channel during LOCA
Creators
- 1. School of Mechanical Engineering, Shiraz University, P.O.B. 7193616548, Shiraz (Iran, Islamic Republic of)
Description
Highlights: • Application of CuO nanoparticles as a complement to the flow field in a PWR core channel under the loss of coolant accident. • Improvement of safety margins in post LOCA where residual heat removal system failure may occur. • Simulation of boiling flow which led to dryout phenomenon with an Eulerian–Eulerian approach for each phase. - Abstract: Forced convection boiling and critical heat flux have been under considerable attention in variety of areas due to high heat removal capacity. However, once the heat flux exceeds a certain high level (CHF), the heated surface can no longer support continuous liquid contact, associated with substantial reduction in the heat transfer efficiency. One way to increase the level of the CHF is to add certain nanoparticles to the base fluid. The present paper investigates the effects of the addition of copper oxide nanoparticles on CHF phenomenon within the general-purpose computational fluid dynamics (CFD). The governing equations solved are generalized phase continuity, momentum and energy equations. Wall boiling phenomena are modeled using the baseline mechanistic nucleate boiling model developed in Rensselaer Polytechnic Institute (RPI). To simulate the critical heat flux phenomenon, the RPI model is extended to the departure from nucleate boiling (DNB) by partitioning wall heat flux to both liquid and vapor phases considering the existence of thin liquid wall film. It was shown that the presence of copper oxide nanoparticles in the base fluid, delays the dryout phenomenon dramatically and in specific concentration, CHF threshold would be enhanced, therefore, raising the upper limit of CHF could allow for higher safety margins.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.pnucene.2015.02.004Additional details
Identifiers
- DOI
- 10.1016/j.pnucene.2015.02.004;
- PII
- S0149197015000384;
Publishing Information
- Journal Title
- Progress in Nuclear Energy
- Journal Volume
- 81
- Journal Page Range
- p. 228-238
- ISSN
- 0149-1970
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51007812
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- AFTER-HEAT REMOVAL; COMPUTERIZED SIMULATION; COPPER OXIDES; CRITICAL HEAT FLUX; DEPARTURE NUCLEATE BOILING; FLUID MECHANICS; FORCED CONVECTION; LIQUIDS; LOSS OF COOLANT; NANOPARTICLES; PWR TYPE REACTORS; RHR SYSTEMS; SAFETY MARGINS; THREE-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW; WALLS; WATER
- Descriptors DEC
- ACCIDENTS; BOILING; CHALCOGENIDES; CONVECTION; COOLING SYSTEMS; COPPER COMPOUNDS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUIDS; HEAT FLUX; HEAT TRANSFER; HYDROGEN COMPOUNDS; MASS TRANSFER; MECHANICS; NUCLEATE BOILING; OXIDES; OXYGEN COMPOUNDS; PARTICLES; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; SIMULATION; THERMAL REACTORS; TRANSITION ELEMENT COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Copyright © 2015 Elsevier Ltd. All rights reserved.