Published 1991
| Version v1
Journal article
Investigations on the critical heat flux of an APWR - results of the KRISTA-program
- 1. Kernforschungszentrum Karlsruhe GmbH (Germany). Inst. fuer Reaktorbauelemente (IRB)
- 2. Technische Univ. Braunschweig (Germany)
Description
The KRISTA program has been applied for experiments on the critical heat flux in 8 mm circular tubes and in seven-rod fuel bundle arrangements, in order to establish basic data on CHF within the parametric scope of the APWR design concept. (orig.)
Abstract (German)
Im KRISTA-Programm wurden bislang experimentelle Untersuchungen zur kritischen Heizflaechenbelastung in 8 mm Kreisrohren und in 7-Stabbuendeln durchgefuehrt. Ziel dieser Arbeiten war es, grundlegende Kenntnisse zur kritischen Heizflaechenbelastung im Parameterbereich des fortgeschrittenen Druckwasserreaktors (FDWR) zu erarbeiten. (orig.)Additional details
Additional titles
- Original title (German)
- Untersuchungen zur kritischen Heizflaechenbelastung eines FDWR - Ergebnisse des KRISTA-Programms
Publishing Information
- Journal Title
- KFK (Kernforschungszentrum Karlsruhe) Nachrichten
- Journal Volume
- 23
- Journal Issue
- 1
- Series
- KFK Nachr.
- Journal Page Range
- 44-50
- ISSN
- 0340-756X
- CODEN
- KFKNA
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 23012010
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRITICAL HEAT FLUX; DEPARTURE NUCLEATE BOILING; FILM BOILING; HCLWR TYPE REACTORS; HEXAGONAL LATTICES; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS
- Descriptors DEC
- BOILING; CRYSTAL LATTICES; CRYSTAL STRUCTURE; ENRICHED URANIUM REACTORS; HEAT FLUX; NUCLEATE BOILING; PHASE TRANSFORMATIONS; PLUTONIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS