Condensation efficiency in two-phase computer code FRACAS
- 1. Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Paris-la-Defense (France)
Description
In order to achieve a better understanding and quantification of the safety injection efficiency, the COSI test program has been launched, with test conditions representative of both actual cold leg SI geometries and typical small break conditions. The results of the first test series have shown relatively high SI efficiency, amounting to almost perfect condensation in a lot of cases. The phenomenology of the concensation process has been established and divided into four contributors : on the SI jet itself, in the mixing zone created by the impact of the jet, in the cold leg outside the mixing zone, and finally in the downcomer in case of low liquid level. After data reduction, the thermalhydraulic network code FRACAS has been modified with the condensation model derived from the COSI tests. A typical small break calculation has been performed which shows a significant improvement in terms of core mass inventory due to direct and indirect effects of greater SI efficiency, and demonstrates the conservatism of the current model. (orig.)
Additional details
Publishing Information
- Publisher
- Braun.
- Imprint Place
- Karlsruhe (Germany, F.R.)
- ISBN
- 3-7650-1116-9
- Imprint Title
- Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 2
- Imprint Pagination
- 696 p.
- Journal Page Range
- p. 1042-1046.
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
- 22038380
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; FLOW RATE; HIGH PRESSURE COOLANT INJECTIO; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; TWO-PHASE FLOW; VAPOR CONDENSATION
- Descriptors DEC
- ACCIDENTS; ECCS; ENRICHED URANIUM REACTORS; FLUID FLOW; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS