Reflooding tests on WWER fuel subassembly models
- 1. Institute of Physics and Power Engineering (IPPE), Obninsk (Russian Federation)
Description
The paper presents the results of experimental and calculational studies of reflooding phenomenon in a WWER fuel subassembly model consisting of 7 rods. A description of equipment used and test procedures is given. Electrically heated rods (indirect heating) of a capacity of 10 kW with a stepwise axial power generation are employed as heater rods. Each heater rod is provided with 6 surface thermocouples installed on 3-6 levels. Data collection and processing is implemented by a fast-response system based on PC-486 compatible IBM with an input-output frequency of 90 kHz. In the course of tests, a study was performed on the effect of the initial power generation, pressure, flooding rate, inlet coolant temperature, the number and position of non-heated rods, and the perforated plate at the test section exit on the rate of wetting front and the thermal behaviour of heater rods. The experimental results obtained were compared with the calculations performed using the RELAP5/Mod3 Code. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Eighth international topical meeting on nuclear reactor thermal-hydraulics
- Imprint Pagination
- 1890 p.
- Journal Page Range
- p. 1440-1447
Conference
- Title
- 8. international topical meeting on nuclear reactor thermal-hydraulics
- Acronym
- NURETH-8
- Dates
- 30 Sep - 4 Oct 1997
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 30004368
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPARATIVE EVALUATIONS; FLOODS; FUEL ASSEMBLIES; FUEL RODS; HEAT TRANSFER; R CODES; SIMULATION; TEST FACILITIES; VERIFICATION; WWER TYPE REACTORS
- Descriptors DEC
- COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVALUATION; FUEL ELEMENTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Published in 3 volumes