Mathematical modeling of CANDU-PHWR
Description
The paper deals with the transient studies of CANDU 600 pressurized Heavy Water Reactor (PHWR). This study involved mathematical modeling of CANDU-PHWR to study its thermodynamic performances. Modeling of CANDU-PHWR was based on lumped parameter technique. The reactor model includes the neutronic, reactivity, and fuel channel heat transfer. The nuclear reactor power was modelled using the point kinetics equations with six groups of delayed neutrons and the reactivity feed back due to the changes in the fuel temperature and coolant temperature. The CANDU-PHWR model was coded in FORTRAN language and solved by using a standard numerical technique. The adequacy of the model was tested by assessing the physical plausibility of the obtained results. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-77-1
- Imprint Title
- 8. International conference on CANDU fuel. Conference proceedings
- Imprint Pagination
- 120 Megabytes
- Journal Page Range
- p. 211-219
Conference
- Title
- 8. international conference on CANDU fuel
- Dates
- 21-24 Sep 2003
- Place
- Honey Harbour, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 36074073
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; FUEL CHANNELS; HEAT TRANSFER; MATHEMATICAL MODELS; NEUTRON FLUX; PHWR TYPE REACTORS; THERMODYNAMICS; TRANSIENTS
- Descriptors DEC
- ENERGY TRANSFER; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION FLUX; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 7 refs., 4 figs.