Results 251 to 260 of about 19,514,073 (287)
Some of the next articles are maybe not open access.
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
openaire +2 more sources
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.
openaire +1 more source
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
openaire +1 more source
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
openaire +1 more source
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
openaire +1 more source
Development and validation of safety grade decay heat removal system model of SFR
Annals of Nuclear EnergyAnurag Samantara, K. Natesan
openaire +3 more sources
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
openaire +1 more source
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
openaire +1 more source
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
openaire +1 more source
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
openaire +1 more source