On the characteristics of the flow and heat transfer in the core bypass region of a PWR
- 1. Laboratory for Reactor Physics and Systems Behaviour (LRS), Paul Scherrer Institut, 5232 Villigen PSI (Switzerland)
Description
Highlights: • Initial CFD results for flow in the core bypass of a Siemens KWU PWR are presented. • The flow and heat transfer between the core shroud and core barrel is investigated. • Flow conditions in the core bypass are in the transition-to-turbulence regime. • Vortex shedding taking place downstream of the core formers. • The influence of the bypass temperatures on the neutron fluence is non-negligible. - Abstract: The development of analysis models for the Swiss reactors is a key objective of the STARS project at the Paul Scherrer Institut (PSI). Within this context there is a need for the development of computational fluid dynamics (CFD) models of the Swiss reactors in support of future high fidelity investigations of steady-state and transient scenarios. This article presents initial results for the CFD analysis of a Siemens KWU PWR with a focus on the flow behaviour and heat transfer in the gap between the core shroud and core barrel. Temperatures and densities in this region of the reactor are important, for example, for accurate estimations of fast neutron fluence and activation in the steel structures of the core shroud, core barrel and reactor pressure vessel. The flow behaviour in this region may also be relevant for better understanding of ex-core detector responses. The flow conditions in the core bypass region were found to be in the transition-to-turbulence regime, with vortex shedding taking place downstream of the core formers as a result of flow instabilities. The non-stationary nature of the flow presented a challenge in terms of obtaining a solution within a reasonable time period. Two approaches were proposed to address this challenge: time-averaging of the flow-field information before solving the conjugate heat transfer problem; time-averaging of surface heat fluxes in order to derive detailed surface heat transfer coefficients. Both approaches yielded similar results with similar computational effort. Several characteristics and features of the core bypass flow are discussed. Updated Monte Carlo simulation results show that the influence of the core bypass temperatures on the neutron fluence predictions is non-negligible. This highlights the importance of including accurate bypass temperatures in future Monte Carlo simulations focused on ex-core regions.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2018.01.039Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2018.01.039;
- PII
- S0029549318300529;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 330
- Journal Page Range
- p. 117-128
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50082111
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- BYPASSES; COMPUTERIZED SIMULATION; DRILLING EQUIPMENT; FAST NEUTRONS; FLUID MECHANICS; FUEL STORAGE POOLS; HEAT TRANSFER; MONTE CARLO METHOD; NEUTRON FLUENCE; NUCLEAR INDUSTRY; PRESSURE VESSELS; PWR TYPE REACTORS; REACTIVITY; SHROUDS; SPENT FUEL STORAGE; TEMPERATURE MONITORING
- Descriptors DEC
- BARYONS; CALCULATION METHODS; CONTAINERS; COOLING SYSTEMS; ELEMENTARY PARTICLES; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FERMIONS; HADRONS; INDUSTRY; MECHANICS; MONITORING; NEUTRONS; NUCLEONS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; STORAGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- © 2018 Elsevier B.V. All rights reserved.