Published 1989
| Version v1
Book
PWR'S core incidental transients modelization using the THYC software
Creators
- 1. Electricite de France, 92 - Clamart. Direction des Etudes et Recherches
- 2. Electricite de France, 78 - Chatou
Description
EDF has developed THYC, Thermal HYdraulic code for the Core, which is a new computer code designed to study the three dimensional thermal hydraulic behavior of cores in PWR or LMFBR. THYC can also be used to analyze experiments on models to increase our knowledge of thermal hydraulics for electricity production. This paper presents the calculations which were asked in the schedule of conditions; they were run with a 900 megawatt PWR geometry. Different causes of boiling were tested: pressure diminution, mass flow reduction, high energy. These transients give valuable computed results which allows to carry on THYC validation program. (orig.)
Additional details
Publishing Information
- Publisher
- Braun.
- Imprint Place
- Karlsruhe (Germany, F.R.)
- ISBN
- 3-7650-1115-0
- Imprint Title
- Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 1
- Imprint Pagination
- 745 p.
- Journal Page Range
- p. 255-260.
Conference
- Title
- 4. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4).
- Dates
- 10-13 Oct 1989.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 22029453
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; HYDRAULICS; LOSS OF COOLANT; NUMERICAL SOLUTION; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY EXPERIMENTS; SUBCOOLED BOILING; VERIFICATION
- Descriptors DEC
- ACCIDENTS; BOILING; ENRICHED URANIUM REACTORS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS