DocumentCode :
1342914
Title :
Effect of Loop Configuration on Steam Drum Level Control for a Multiple Drum Interconnected Loops Pressure Tube Type Boiling Water Reactor
Author :
Gaikwad, Avinash J. ; Vijayan, P.K. ; Iyer, Kannan ; Bhartiya, Sharad ; Kumar, Rajesh ; Lele, H.G. ; Ghosh, A.K. ; Kushwaha, H.S. ; Sinha, R.K.
Author_Institution :
Reactor Safety Div., BARC, Mumbai, India
Volume :
56
Issue :
6
fYear :
2009
Firstpage :
3712
Lastpage :
3725
Abstract :
For AHWR (Advanced Heavy Water Reactor), a pressure tube type Boiling Water Reactor (BWR) with parallel inter-connected loops, the Steam Drum (SD) level control is closely related to Main Heat Transport (MHT) coolant inventory and sustained heat removal through natural circulation, hence overall safety of the power plant. The MHT configuration with multiple (four) interconnected loops influences the SD level control in a manner which has not been previously addressed. The MHT configuration has been chosen based on comprehensive overall design requirements and certain Postulated Initiated Event (PIEs) for Loss of Coolant Accident (LOCA), which postulates a double ended break in the four partitioned Emergency Core Cooling System (ECCS) header. A conventional individual three-element SD level controller can not account for the highly coupled and interacting behaviors, of the four SD levels. An innovative three-element SD level control scheme is proposed to overcome this situation. The response obtained for a variety of unsymmetrical disturbances shows that the SD levels do not diverge and quickly settle to the various new set points assigned. The proposed scheme also leads to enhanced safety margins for most of the PIEs considered with a little influence on the 100% full power steady-state design conditions.
Keywords :
fission reactor accidents; fission reactor coolants; fission reactor cooling; fission reactor design; heavy water reactors; level control; light water reactors; nuclear power stations; physical instrumentation control; AHWR; Advanced Heavy Water Reactor; BWR; ECCS; LOCA; MHT coolant; PIE; emergency core cooling system; heat removal; loss of coolant accident; main heat transport coolant; natural circulation; nuclear power plant safety; parallel interconnected loops; postulated initiated event; pressure tube type Boiling Water Reactor; steady-state design condition; steam drum level control; three-element SD level controller; Accidents; Analytical models; Coolants; Inductors; Level control; Power generation; Power system modeling; Safety; Transient analysis; Water heating; BWR; RELAP5; innovative three-element steam drum level control; modeling simulation control of nuclear power plants; plant transient and safety analysis; thermal hydraulics;
fLanguage :
English
Journal_Title :
Nuclear Science, IEEE Transactions on
Publisher :
ieee
ISSN :
0018-9499
Type :
jour
DOI :
10.1109/TNS.2009.2033682
Filename :
5341437
Link To Document :
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