Published July 1997
| Version v1
Journal article
Post test calculations to 11% break loca experiments on the integral test facility ISB-VVER using the thermalhydraulic code ATHLET
Description
The considered test was a break on the upper plenum with different modes of emergency core cooling. The reference case was the non-availability of emergency cooling. Injecting the emergency coolant into the cold leg, no increasing of rod cladding temperatures was observed, but natural circulation instabilities occurred. Injecting the cooling into the hot leg, the cooling situation was getting worse. Due to the injected cold emergency coolant, the fluid density in the discharge volume was enhanced and the break mass flow increased. The observed events in the test were reproduced by the code with good agreement. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 170
- Journal Issue
- 1-3
- Journal Page Range
- p. 3-7.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- Research and technology - our future.
- Original Conference Title
- Jahrestagung Kerntechnik (JK '95) - Gemeinsame Veranstaltung des Deutschen Atomforums e.V. (DAtF) und der Kerntechnischen Gesellschaft e.V. (KTG): Forschung und Technik - unsere Zukunft
- Acronym
- Annual meeting on nuclear technology '95 - joint meeting of Deutsches Atomforum e.V. (DAtF) and Kerntechnische Gesellschaft e.V. (KTG)
- Dates
- 17-18 May 1995.
- Place
- Nuremberg (Germany).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Switzerland
- INIS RN
- 28061960
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; COOLANT LOOPS; ECCS; LOSS OF COOLANT; NATURAL CONVECTION; REACTOR SAFETY EXPERIMENTS; TEMPERATURE DISTRIBUTION; TEMPERATURE RANGE 0400-1000 K; TEST FACILITIES; VOID FRACTION; WWER-5 REACTOR
- Descriptors DEC
- ACCIDENTS; CONVECTION; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT TRANSFER; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SIMULATION; TEMPERATURE RANGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS