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Passive System Reliability Analysis: a Study on Decay Heat Removal Passive Systems
, 2000 This paper deals with the reliability assessment of passive systems that have been developed in the recent years by suppliers, industries, utilities and research organisations, aiming at plant safety improvement and substantial simplification in its implementation.
Burgazzi, L.
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Design of a Decay Heat Removal System for EFIT Plant
Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 2009The Integrated Project EUROTRANS, funded by the European Commission as part of the 6th European framework program, provides the advanced design of a multi purpose research oriented Accelerator Driven System (ADS), called XT-ADS (eXperimenTal-ADS), and the preliminary design of an industrial scale ADS, called EFIT (European Facility for Industrial ...
B. LEONCINI +3 more
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The Choose of Decay Heat Removal Systems of SFR
Volume 6A: Thermal-Hydraulics and Safety Analyses, 2018A sodium-cooled fast reactor is a significant candidate for future power reactor systems. Decay heat removal is an essential function of reactor safety systems The decay heat removal system should have the capacity to remove the decay heat with natural circulation in any accident.
Nina Yue +4 more
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Numerical simulations of an innovative decay heat removal systems
The European Physical Journal Plus, 2020The general interest in innovative forms of nuclear energy from fission leads many industrial companies and research institutions to develop ambitious projects to design an innovative reactor fleet. Often such new designs are based on innovative reactor coolants and imply as a consequence a complete change of the technology know how.
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Control of decay heat removal through alternate system in PFBR
Nuclear Engineering and Design, 2013Abstract In the Prototype Fast Breeder Reactor (PFBR) decay heat is removed directly from the reactor core through Safety Grade Decay Heat Removal (SGDHR) circuit. Operation Grade Decay Heat Removal (OGDHR) system offers an alternate decay heat removal path using the heat removal capacity of the main heat transport system. It is preferred path during
T. Somavathi +5 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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Risk-reduction of passive decay heat removal system by using gallium-water for UCFR and SMR
International Journal of Energy Research, 2017 Employing a gallium-based passive decay heat removal system (PDHRS), which enables the use of water as an ultimate heat sink, was proposed for the UCFR-100. The gallium-based PDHRS has replaced the previous sodium-based PDHRS.
Seok Bin Seo, In Guk Kim, In Cheol Bang
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Transient Analysis of Passive Decay Heat Removal System for CEFR
Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, 2013A passive decay heat removal system (DHRS) has been installed on Chinese Experimental Fast Reactor (CEFR). To well predict the thermal-hydraulics behavior of DHRS in transient, an integrated model has been developed for CEFR by using OASIS code. The model included the main thermal transfer system and DHRS circuit.
H. Qian, Z. Li, L. Ren
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Development and validation of safety grade decay heat removal system model of SFR
Annals of Nuclear EnergyAnurag Samantara, K. Natesan
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A study on reliability assessment of a decay heat removal system for a sodium-cooled fast reactor
Annals of Nuclear Energy, 2018 Probabilistic risk assessment is expected to play a major role in the design and regulation framework for future reactors. Since the safety of a sodium-cooled fast reactor largely depends on the reliability of a decay heat removal system, which adopts a ...
Jintae Kim, Moosung Jae
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