Results 11 to 20 of about 24,364 (164)
MANAGING A PROLONGED STATION BLACKOUT CONDITION IN AHWR BY PASSIVE MEANS
Nuclear Engineering and Technology, 2013 Removal of decay heat from an operating reactor during a prolonged station blackout condition is a big concern for reactor designers, especially after the recent Fukushima accident.
MUKESH KUMAR +4 more
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Dynamic Hybrid Reliability Studies of a Decay Heat Removal System [PDF]
International Journal of Reliability, Quality and Safety Engineering, 2015 Some critical safety systems exhibit the characteristics of hybrid stochastic class whose performance depends on the dynamic interactions of deterministic variables of physical phenomena and probabilistic variables of system failures. However, conventional probabilistic safety assessment (PSA) method involves static event and linked fault tree analysis
Kumar, Ranjan +4 more
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Nuclear Engineering and Technology, 2019 The air-cooled passive decay heat removal system (APDHR) was proposed to provide the ultimate heat sink for non-LOCA accidents. The APDHR is a modified one of Passive Auxiliary Feed-water system (PAFS) installed in APR+.
Do Yun Kim +3 more
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Long-term decay heat removal in a submerged SMR [PDF]
Annals of Nuclear Energy, 2019 Abstract Following the Fukushima-Daiichi nuclear accident in March 2011, innovations are needed to improve the reliability of new generation nuclear power plants toward scenarios where electrical power and ultimate heat sink are lost. This paper describes an integral design and basic passive safety strategy of a Small Modular Reactor (SMR) submerged ...
marco santinello, marco ricotti
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Water film covering characteristic on horizontal fuel rod under impinging cooling condition
Nuclear Engineering and Technology, 2022 Jet impinging device is designed for decay heat removal on horizontal fuel rods in a low temperature heating reactor. An experimental system with a fuel rod simulator is established and experiments are performed to evaluate water film covering capacity ...
Penghui Zhang +5 more
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Characteristic analysis of natural circulation residual heat removal in small reactor
International Journal of Advanced Nuclear Reactor Design and Technology, 2022 In order to study the characteristics of small helium-xenon cooled nuclear reactor that only relies on natural circulation to remove residual heat after shutdown, this paper carries out geometric and physical modeling of helium-xenon cooled nuclear ...
Haoyang Liao +5 more
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Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout
Journal of Nuclear Engineering and Radiation Science, 2021 Abstract As part of the European sodium fast reactor (ESFR)-safety measures assessment and research tools (SMART) project, safety assessments are being conducted on the updated ESFR design. An important part of the study is the evaluation of the reactor's behavior within hypothetical accidental conditions to assess and ensure that the ...
Bodi, Janos +3 more
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Mechanical Engineering Journal, 2022 A direct reactor auxiliary cooling system (DRACS) under natural circulation (NC) conditions with a dipped-type direct heat exchanger (D-DHX) in the upper plenum of a reactor vessel (RV) has been investigated for enhancing the safety of sodium-cooled fast
Erina HAMASE +5 more
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Decay Heat Removal and Transient Analysis in Accidental Conditions in the EFIT Reactor
Science and Technology of Nuclear Installations, 2008 The development of a conceptual design of an industrial-scale transmutation facility (EFIT) of several 100 MW thermal power based on accelerator-driven system (ADS) is addressed in the frame of the European EUROTRANS Integral Project. In normal operation,
Giacomino Bandini +5 more
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Simulation of Steady States of Helium Loop at Long Time Scenarios [PDF]
MATEC Web of Conferences, 2020 The natural circulation helium loop is an experimental facility designed for the research of the possibility of utilizing natural convection cooling for the case of decay heat removal from a fast nuclear reactor.
Világi František +6 more
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