Quenching of rod bundles with fuel rod simulators of different design
Description
Reflood tests with 5 x 5 rod bundles consisting of electrically heated full length fuel rod simulators with Zircaloy claddings and a helium filled gap between cladding and internal Al2O3 pellets have been performed previously. For these tests the same facility has been used as for tests carried out previously with a 5 x 5 rod bundle consisting of rods with stainless steel claddings without gap between cladding and MgO insulation. The reflood parameters, e.g. bundle power, system pressures, flooding velocities were the same for both types of rod bundles. A comparison of selected data measured as well as evaluated from tests of both the bundles shows the following: Fuel rod simulators with Zircaloy claddings and a helium filled gap underneath the claddings quench significantly earlier than gapless fuel rod simulators with thick stainless steel claddings. Quenching is initiated from a higher level of the heat stored prior to quenching of rods with a gap
Additional details
Publishing Information
- Imprint Title
- First international workshop on fundamental aspects of post-dryout heat transfer: proceedings
- Journal Page Range
- p. 171-178.
- 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
- 16068535
- 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; LOSS OF COOLANT; PWR TYPE REACTORS; QUENCHING; REACTOR SAFETY; SIMULATION; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALLOYS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUEL ELEMENTS; HEAT TREATMENTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS