Reflooding of a PWR bundle: Pericles programme and first results
Creators
Description
Pericles programme aims at studying the thermohydraulics of a pressurized water reactor core during emergency core cooling, in case of large as well as small breaks. To meet this objective, Pericles facility which is capable of withstanding pressures up to 70 bar and can be equipped with either a cylindrical or a rectangular test section was built. The cylindrical test section will consist of a 368 heater rod bundle, full length, 17 x 17 geometry, together with 25 thimble tubes, and will be used from 1984 to mainly investigate core thermohydraulics in case of small breaks. The rectangular one, in operation since mid 1982, is composed of 357 heater rods which are arranged in three 7 x 17 assemblies, and is devoted to the study of two-dimensional phenomena in the core
Additional details
Publishing Information
- Imprint Title
- Proceedings of the eleventh water reactor safety research information meeting. Volume 1
- Journal Page Range
- p. 402-427.
- Report number
- NUREG/CP--0048-Vol.1
Conference
- Title
- 11. NRC water reactor safety research information meeting.
- Dates
- 14-24 Oct 1983.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16006993
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ECCS; FUEL ASSEMBLIES; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY; RESEARCH PROGRAMS; STEAM; TESTING; TRANSIENTS; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS