Development of the APSRA+ Methodology for Passive System Reliability Analysis and Its Application to the Passive Isolation Condenser System of an Advanced Reactor-Reference-Cited by-同舟云学术

Development of the APSRA+ Methodology for Passive System Reliability Analysis and Its Application to the Passive Isolation Condenser System of an Advanced Reactor

Published:2016-04 Issue:1 Volume:194 Page:39-60
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Chandrakar A.¹,Nayak A. K.²,Gopika Vinod³

Affiliation:

1. Homi Bhabha National Institute, Anushaktinagar, Mumbai 400094, India

2. Bhabha Atomic Research Centre, Reactor Engineering Division, Trombay, Mumbai 400085, India

3. Bhabha Atomic Research Centre, Reactor Safety Division, Trombay, Mumbai 400085, India

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT15-80

Reference13 articles.

1. “Safety Related Terms for Advanced Nuclear Power Plant,” IAEA-TECDOC-626, International Atomic Energy Agency (1991).

2. F. D’AURIA and G.M. GALASSI, “Methodology for the Evaluation of the Reliability of Passive Systems,” DIMNP, NT420 (00), University of Pisa (2000).

3. R. W. SHUMWAY, “Variable Properties Laminar Gas Flow Heat Transfer and Pressure Drop in Annuli,” EMMT Lab TR 3, University of Arizona (1969).

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