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The Choose of Decay Heat Removal Systems of SFR

Volume 6A: Thermal-Hydraulics and Safety Analyses, 2018
A 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
openaire   +1 more source

RELAP5 assessment on CIRCE decay heat removal experiments

2014
DHR experiments were carried out on the large scale LBE-cooled CIRCE facility at the ENEA/Brasimone center to verify the decay heat removal through heat exchangers immersed in the LBE pool under representative accidental conditions, and provide a valuable database for both CFD and system code assessment.
Di Piazza, I.   +4 more
openaire   +2 more sources

Control of decay heat removal through alternate system in PFBR

Nuclear Engineering and Design, 2013
Abstract 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, 2013
A 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

Analysis of DRACS and DRACS-RVACS Decay Heat Removal Experiments

Nuclear Technology, 1991
This paper reports on two large-scale decay heat removal experiments analyzed to support the validation of the thermal-hydraulic code COMMIX and the design of advanced liquid metal reactors (ALMRs). The experiments were performed in the reactor vessel auxiliary cooling system (RVACS) test facility, which provides a scaled simulation of the passive ...
Constantine P. Tzanos, Dean R. Pedersen
openaire   +1 more source

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, 2009
The 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

Scaling of Natural Circulation Decay Heat Removal From Coolant Pools

Thermal Hydraulics of Advanced Nuclear Reactors, 1994
Abstract This paper presents the generic features together with the basic physical phenomena of nuclear decay heat removal from large coolant pools by natural circulation. Using dimensionless numbers such as the Richardson number, the Stanton number and a relevant time scale, the local and the overall thermo-hydraulic aspects of pool ...
Knebel, J. U., Weinberg, D., Müller, U.
openaire   +1 more source

Introduction of IDINHX, A New Heat Exchanger for Passive Decay Heat Removal

Nuclear Technology, 2008
Decay heat removal in a nuclear plant is very important, and the performance of a decay heat removal system in a plant is a critical factor for the plant safety. In designing the decay heat removal system, a passive-type system is usually more difficult than an active-type system, and there can be additional restrictions in designing plant systems for ...
openaire   +1 more source

INNOVATIVE RADIATION-BASED DECAY HEAT REMOVAL SYSTEM

2012
One of the main issues, regarding the development of Generation IV nuclear power plants, is the safety. In order to design nuclear systems characterized by enhanced safety features, an innovative and passive system, aimed at decay heat removal, especially suitable for sodium cooled fast reactors, has been developed. The attention is here mainly focused
DE SANTIS, ANDREA   +4 more
openaire   +1 more source

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