Published February 2018 | Version v1
Journal article

Analysis of flow blockage accidents in rectangular fuel assembly based on CFD methodology

  • 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.2017.09.012

Additional 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.