Published 1999
| Version v1
Miscellaneous
An unequal-velocity equal-temperature model for simulation of CANDU fuel channel thermohydraulic behaviour
Creators
- 1. Power Engineering Faculty, University 'Politehnica' of Bucharest, Splaiul Independentei 313, Sector 6, RO-77206 Bucharest (Romania)
Description
A model for the thermal-hydraulic behaviour of a CANDU fuel channel is presented. A single-phase or a two-phase flow model is transformed into a low order dynamical system of ordinary differential equations. This model is applied to simulation of thermal-hydraulic CANDU fuel channel transients. Some typical results are reported and compared with the predictions of FIREBIRD code. (authors)
Availability note (English)
Available from authors or Romanian Association Nuclear Energy - AREN, 33 Magheru Blvd., Sector 1, RO-70164 Bucharest (RO)Additional details
Publishing Information
- Publisher
- Romanian Association 'Nuclear Energy' - AREN, University 'Politehnica' of Bucharest
- Imprint Place
- Bucharest (Romania)
- Imprint Title
- SIEN '99 - INTERNATIONAL SYMPOSIUM ON NUCLEAR ENERGY. NPP Operation and Maintenance. Part II
- Imprint Pagination
- 192 p.
- Journal Page Range
- p. 414-419
Conference
- Title
- SIEN '99 - International Symposium on Nuclear Energy. NPP Operation and Maintenance
- Dates
- 15-16 Oct 1999
- Place
- Bucharest (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 31006957
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; DIFFERENTIAL EQUATIONS; F CODES; FLOW MODELS; FLOW RATE; FUEL CHANNELS; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; TEMPERATURE DEPENDENCE; THERMAL ANALYSIS; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; ENERGY TRANSFER; EQUATIONS; MATHEMATICAL MODELS; REACTOR CHANNELS; REACTOR COMPONENTS; SIMULATION
Optional Information
- Notes
- 9 refs., 6 figs.