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Decay heat removal in pool type fast reactor using passive systems
Nuclear Engineering and Design, 2012Abstract Post shutdown decay heat removal in a fast reactor is one of the most important safety functions which must be accomplished with a very high reliability. To achieve high reliability, the fast breeder reactor design has emphasized on passive or near passive decay heat removal systems utilizing the natural convection in the heat removal path ...
U. Parthasarathy +5 more
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Risk-Informed Design Changes in a Passive Decay Heat Removal System
Nuclear Technology, 2008The failure probability of a passive decay heat removal (DHR) system after a loss-of-coolant accident (LOCA) is evaluated as part of a risk-informed design process for a helium-cooled fast reactor....
Giovanbattista Patalano +2 more
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A passive decay heat removal system for LWRs based on air cooling
Nuclear Engineering and Design, 2015Abstract The present paper describes the capability of an air cooling system (ACS) to remove decay heat from a core of LWR such as an advanced boiling water reactor (ABWR) and a pressurized water reactor (PWR). The motivation of the present research is the Fukushima severe accident (SA) on 11 March 2011.
Hiroyasu Mochizuki, Takahiro Yano
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Experimental study on the transient response of passive decay heat removal system
Nuclear Engineering and Design, 2014Abstract The safety grade decay heat removal system (SGDHR) of prototype fast breeder reactor will be kept in a poised state during normal operating conditions with a small sodium flow in the SGDHR secondary system. Followed by a reactor trip, damper provided at air side of sodium to air heat exchanger opens and the air flow through AHX and sodium ...
V. Vinod +4 more
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Design and evaluation of Operation Grade Decay Heat Removal System of PFBR
Nuclear Engineering and Design, 2011Abstract The decay heat removal (DHR) system removes the decay heat generated (by radioactive decay of fission products) in the core after the reactor is shut down, thereby ensuring proper cooling of the core sub assemblies and limiting main vessel, internals and sodium temperature within safe limits.
L. Satish Kumar +4 more
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Materials Today: Proceedings, 2020
Abstract In nuclear power plant, as the core temperature increases exponentially during pump failure/plant shutdown, there must be an efficient decay heat removal mechanism so as to avoid severe accidents. In this scenario natural circulation loops find its importance as it is a passive heat transport mechanism with no moving parts. Further, based on
D.N. Elton +2 more
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Abstract In nuclear power plant, as the core temperature increases exponentially during pump failure/plant shutdown, there must be an efficient decay heat removal mechanism so as to avoid severe accidents. In this scenario natural circulation loops find its importance as it is a passive heat transport mechanism with no moving parts. Further, based on
D.N. Elton +2 more
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An Optimal Design Approach for the Decay Heat Removal System in PGSFR
Volume 1C, Symposia: Fundamental Issues and Perspectives in Fluid Mechanics; Industrial and Environmental Applications of Fluid Mechanics; Issues and Perspectives in Automotive Flows; Gas-Solid Flows: Dedicated to the Memory of Professor Clayton T. Crowe; Numerical Methods for Multiphase Flow; Transport Phenomena in Energy Conversion From Clean and Sustainable Resources; Transport Phenomena in Materials Processing and Manufacturing Processes, 2014Sodium-cooled Fast Reactor (SFR) is one of the generation IV (Gen-IV) nuclear reactors. Prototype Gen-IV SFR (PGSFR) is a SFR being developed in Korea Atomic Energy Research Institute (KAERI). Decay Heat Removal System (DHRS) in the PGSFR has a safety function to make shutdown the reactor under abnormal plant conditions.
Dehee Kim, Jaehyuk Eoh, Tae-Ho Lee
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Investigations of accelerator reliability and decay heat removal for accelerator-driven system
Annals of Nuclear Energy, 2019Abstract To realize the feasible accelerator-driven system (ADS) concept, the investigations for the reliable accelerator and conceptual plant design considering safety issues were performed. As the reliable accelerator concept, the double-accelerator concept was proposed to reduce the beam-trip frequency.
Takanori Sugawara +2 more
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Simulation Model of a Passive Decay Heat Removal System for Lead-Cooled Fast Reactors
Volume 6: Energy, Parts A and B, 2012The generation IV lead cooled fast reactors are of particular interest for the Italian research: several influential companies (Ansaldo Nucleare, ENEA) are involved in these important European R&D projects. At present, one significant European project in progress is LEADER (Lead cooled European Advanced DEmonstrator Reactor) which includes, among ...
DAMIANI, LORENZO, PINI PRATO, ALESSANDRO
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A passive decay heat removal system for the lead cooled fast reactor demonstrator “Alfred”
Progress in Nuclear Energy, 2015Abstract The generation IV lead cooled fast reactors are of particular interest for the Italian research. At present, one significant European project in progress is LEADER (Lead cooled European Advanced DEmonstrator Reactor) which includes, among its goals, the construction of a lead-cooled fast reactor demonstrator, ALFRED (Advanced Lead Fast ...
DAMIANI, LORENZO +3 more
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