Analysis of flow blockage accidents in rectangular fuel assembly based on CFD methodology
Creators
- 1. School of Nuclear Science and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049 (China)
- 2. Nuclear Power Institute of China, Chengdu 610213 (China)
Description
Highlights: • Flow blockage accidents in rectangular fuel assembly were investigated thoroughly. • RELAP5 calculation was performed and showed good agreement with CFD study. • Effects of locations and types of obstruction in the channel were analyzed deeply. • DNBR curve in the obstructed channel was predicted successfully. - Abstract: Flow blockage accidents in rectangular fuel assembly were investigated by three-dimensional CFD method in detail. Totally six coolant channels of the fuel assembly were modeled. Meanwhile, in order to make understand of the thermal hydraulic characteristics of the flow blockage accidents comprehensively, three coolant channels which included the obstructed channel were investigated and analyzed thoroughly based on simulation results. RELAP5 calculation was performed here to compare with CFD simulation results under non-blocked condition, and the comparison results indicated approximate agreement of such two types of results. On the basis of the CFD simulation, velocity and temperature profiles were discussed for some typical blockage cases, and conclusion was drawn that the redistribution of the mass flow rates occurred after the formation of the blockage, and due to the formation of obstruction, temperature of the coolant and the fuel increased rapidly which caused higher peak temperature in the blockage channel. Simultaneously, the increasing flow resistance would lead to the existence of jet-flow and reverse flow in the obstructed channel. In addition, DNBR calculation indicated that heat flux on the cladding surface would not exceed critical heat flux, thus DNB would not occur under the investigated situation.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2017.09.012Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2017.09.012;
- PII
- S030645491630336X;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 112
- Journal Page Range
- p. 71-83
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50079334
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ACCIDENTS; COOLANTS; CRITICAL HEAT FLUX; DEPARTURE NUCLEATE BOILING; FLOW BLOCKAGE; FLOW RATE; FUEL ASSEMBLIES; SIMULATION; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BOILING; FLUID MECHANICS; HEAT FLUX; HYDRAULICS; MECHANICS; NUCLEATE BOILING; PHASE TRANSFORMATIONS
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.