DocumentCode
2535598
Title
Coupled neutronics-thermal hydraulics model of Advanced Heavy Water Reactor for control system studies
Author
Shimjith, S.R. ; Tiwari, A.P. ; Bandyopadhyay, B.
Author_Institution
Reactor Control Div., Bhabha Atomic Res. Centre, Mumbai
Volume
1
fYear
2008
fDate
11-13 Dec. 2008
Firstpage
126
Lastpage
131
Abstract
A coupled neutronics-thermal hydraulics model of advanced heavy water reactor (AHWR) which can be used for control system studies, simulation etc. is presented in this paper. A nodal model is developed for core neutronics and a simple two-phase thermal hydraulics model is developed from first principles. Neutronics-thermal hydraulics coupling is achieved through the void reactivity feedback model. Selection of a suitable nodalization scheme through steady state analysis is discussed, and dynamic response of the model is also presented.
Keywords
dynamic response; fission reactor cooling; advanced heavy water reactor; control system studies; coupled neutronics-thermal hydraulics model; dynamic response; nodalization scheme; reactivity feedback model; two-phase thermal hydraulics model; Control system synthesis; Equations; Fuels; Hydraulic turbines; Inductors; Lattices; Negative feedback; Pins; Power generation; Steady-state;
fLanguage
English
Publisher
ieee
Conference_Titel
India Conference, 2008. INDICON 2008. Annual IEEE
Conference_Location
Kanpur
Print_ISBN
978-1-4244-3825-9
Electronic_ISBN
978-1-4244-2747-5
Type
conf
DOI
10.1109/INDCON.2008.4768813
Filename
4768813
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