Simulation of critical heat flux experiments in Neptune-CFD code
Creators
- 1. Nuclear Research Institute Rez (NRI), Dept. of Thermal Hydraulic Analyses, 250 68 Rez (Czech Republic)
Description
This paper presents a CFD simulation of selected 'Large Water Loop' critical heat flux experiments. Calculations were performed by NEPTUNE-CFD code. The Large Water Loop (LWL) is non-active pressurised-water equipment with technological and thermal parameters corresponding to those of PWR. The CHF experimental facility (a part of the Large Water Loop) has been designed for research into CHF in water flow through a bundle of electrically heated vertical rods. The critical conditions were determined under constant pressure, inlet water temperature and mass flux and for quasi steady-state - by gradually increasing the heat input. The rods are modelled by hollow tubes with direct heating of the wall. Thirteen CHF tests were calculated with NEPTUNE. In all calculated tests, a sudden rise of the wall temperature was observed. Simulations of cases with a higher mass flux were successful. Simulation of cases with a low mass flux indicates that the modelling approach might not be suitable for lower mass fluxes. The results show that NEPTUNE has some potential for predicting boiling flow up to CHF in the geometry of reactor fuel assembly. The presented work was carried out as part of the NURESIM project. NEPTUNE-CFD code is implemented in the NURESIM platform. (authors)
Additional details
Publishing Information
- Imprint Title
- Computational Fluid Dynamics (CFD) in Nuclear Reactor Safety (NRS) - Proceedings of the workshop on Experiments and CFD Code Application to Nuclear Reactor Safety (XCFD4NRS)
- Imprint Pagination
- 1027 p.
- Journal Page Range
- p. 750-761
- Report number
- NEA-Conf--2008-02
Conference
- Title
- Workshop on Experiments and CFD Code Application to Nuclear Reactor Safety
- Acronym
- XCFD4NRS
- Dates
- 10-12 Sep 2008
- Place
- Grenoble (France)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 44098672
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BUBBLE GROWTH; COALESCENCE; COMPUTERIZED SIMULATION; CONVECTION; CRITICAL HEAT FLUX; FLOW MODELS; FLUID MECHANICS; INTERFACES; N CODES; NUCLEATE BOILING; PWR TYPE REACTORS; TEST FACILITIES; TURBULENCE; TWO-PHASE FLOW; VALIDATION; VOID FRACTION; WALLS
- Descriptors DEC
- BOILING; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HEAT FLUX; HEAT TRANSFER; MASS TRANSFER; MATHEMATICAL MODELS; MECHANICS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 refs.