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Gaikwad, Avinash J.; Rajesh Kumar; Vhora, S.F.; Chakraborty, G.
First national conference on nuclear reactor technology2002
First national conference on nuclear reactor technology2002
AbstractAbstract
[en] The 500 MWe Indian pressurised heavy water (PHWR) incorporates many new features as compared to the earlier 220 MWe PHWRs. To evaluate the new design features like reactor stepback (which reduces the reactor power rapidly) and their safety related implications, simulation model development and transient analysis studies are necessary. The paper deals with the details of the mathematical model for SGs and parametric study on turbine trip transient analysis. The studies were carried out after including the proposed new SGPC program similar to 220 MWe PHWR, which gives a 48 kg/ cm2 maximum SG pressure setpoint at zero power without changing the 100% power set pressure
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Gupta, Satish K. (comp.) (Reactor Safety Div., Bhabha Atomic Research Centre, Mumbai (India)); Board of Research in Nuclear Sciences, Department of Atomic Energy, Mumbai (India); 421 p; Nov 2002; p. 381; NRT-1: 1. nuclear reactor safety; Mumbai (India); 25-27 Nov 2002; Abstract prepared
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Book
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Conference
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