Development of Mitsubishi high thermal performance grid. CFD applicability for thermal hydraulic design
Creators
- 1. Nuclear Development Corporation, Tokai, Ibaraki (Japan)
- 2. Mitsubishi Heavy Industries, Ltd., Kobe, Hyogo (Japan)
Description
Mitsubishi has developed a new zircalloy grid spacer for PWR fuel with higher thermal performance. Computational Fluid Dynamics (CFD) evaluation method has been applied for designing of the new lower pressure loss and higher Departure from Nucleate Boiling (DNB) benefit grid spacer. Reduction of pressure loss of grid structures has been examined by CFD. Also, CFD has been developed as a design tool to predict the coolant mixing ability of vane structures, which is to compare the relative peak spot temperatures around fuel rods at the same heat flux condition. Prototype grids were manufactured and several tests, which were pressure loss measurements, cross-flow measurements and freon DNB tests, were conducted to verify CFD predictions. It is concluded that the applicability of the CFD evaluation method for the thermal hydraulic design of the grid is confirmed. (author)
Additional details
Publishing Information
- Journal Title
- JSME International Journal. Series B, Fluids and Thermal Engineering
- Journal Volume
- 45
- Journal Issue
- 3
- Journal Page Range
- p. 586-591
- ISSN
- 1340-8054
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 34009602
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; CRITICAL HEAT FLUX; DEPARTURE NUCLEATE BOILING; DESIGN; DYNAMICS; GRIDS; HYDRODYNAMICS; LIQUID FLOW; PERFORMANCE; PWR TYPE REACTORS; THERMODYNAMICS
- Descriptors DEC
- BOILING; ELECTRODES; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; HEAT FLUX; MECHANICS; NUCLEATE BOILING; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 6 refs., 15 figs.