Analysis of unprotected loss of heat sink accident in compact high temperature reactor cooled under natural circulation of LBE coolant

Author:

Dwivedi D.K.,Gupta Anurag,Umasankari K.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference49 articles.

1. Analysis of the loss of heat sink transients in the secondary circuit of a VVER-1000 using RELAP5/MOD3.2;Abbasi;Ann. Nucl. Energy,2012

2. ASTM Standard Procedure C781-08, 2014. Standard Practice for Testing Graphite and Boronated Graphite Materials for High Temperature Gas-Cooled Nuclear Reactor Components.

3. On the stability and flow reversal of an asymmetrically heated open convection loop;Bau;J. Fluid Mech.,1981

4. Natural circulation studies in a LBE loop for a wide range of temperature;Borgohain;Nucl. Eng. Design,2016

5. Investigation on turbulent heat transfer to lead–bismuth eutectic flows in circular tubes for nuclear applications;Cheng;Nucl. Eng. Des.,2006

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