Published December 1984
| Version v1
Report
Grid spacer effects in reflooding experiments using rod bundles of different fuel rod simulator design
Description
A comparison of the grid spacer effects, investigated previously in the frame of the FEBA program, with those obtained from tests using fuel rod simulators with Zircaloy claddings and helium filled gaps (REBEKA-rods) is made. For such rods, simulating more adequately nuclear fuel rods than gapless heater rods (e.g. FEBA), the variation of the axial temperature profile due to grid spacers is more pronounced during the reflood phase. In a 5 x 5 bundle of REBEKA rods, tested in the FEBA facility, the cladding temperatures were about 20 K up to 100 K lower downstream of the midplane grid spacer than in corresponding FEBA tests. The grid spacers are hot and dry for most time of the dispersed flow regime
Additional details
Publishing Information
- Imprint Title
- First international workshop on fundamental aspects of post-dryout heat transfer: proceedings
- Journal Page Range
- p. 673-682.
- Report number
- NUREG/CP--0060
Conference
- Title
- International workshop on fundamental aspects of post-dryout heat transfer.
- Dates
- 2-4 Apr 1984.
- Place
- Salt Lake City, UT (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16068544
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DRYOUT; FUEL CANS; FUEL ELEMENT CLUSTERS; FUEL RODS; HEAT TRANSFER; HELIUM; HYDRODYNAMICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; SIMULATION; SPACERS; STEAM; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALLOYS; COOLING SYSTEMS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUEL ASSEMBLIES; FUEL ELEMENTS; MECHANICS; NONMETALS; POWER REACTORS; RARE GASES; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS