In the paper the multi-nodal Pressurized Water Reactor (PWR) model called Mann’s model is presented. This models is used for modelling purposes of the heat transfer from fuel to coolant in reactor core. The authors expand widely used in literature approach by defining additional coefficients for the heat transfer model. These parameters approximate the power generation distribution in the PWR reactor core according to the to the reactor control rod bank movement. Authors describe in details proposed methodology for calculation of introduced power distribution coefficients. In the simplest case those coefficients may be equal and constant over time and space of reactor. On the other hand they can be treated as variables that are time and reactor region dependent. By introducing these specific coefficients nodal model of heat transfer gains advanced capabilities that can be efficiently used in design and synthesis of more advanced power control system in nuclear reactor with respect to temperature distribution within the reactor core.
Autorzy
Informacje dodatkowe
- DOI
- Cyfrowy identyfikator dokumentu elektronicznego link otwiera się w nowej karcie 10.1109/mmar.2016.7575166
- Kategoria
- Aktywność konferencyjna
- Typ
- materiały konferencyjne indeksowane w Web of Science
- Język
- angielski
- Rok wydania
- 2016