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Decay heat removal for LMFR under accidents

Izvestiâ Akademii nauk SSSR. Ènergetika
Nuclear reactors of “Proryv” project are positioned as the basis for large scale nuclear energetics with inherent safety, which in particular means “eliminating accident at NPP that require evacuation let alone resettlement of population”, which includes cases of multiple malfunctions.
V. I. Rachkov   +2 more
openaire   +1 more source

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, M. Jae
semanticscholar   +1 more source

Prediction of decay heat removal capabilities for LMFBRs and comparison with experiments

Nuclear Engineering and Design, 1981
Abstract The decay heat removal capability of LMFBR plants is inverstigated in two steps: the transition phase and the established phase of natural circulation. Major parameters affecting the transition phase are briefly reviewed. This paper, then, considers two analytical approaches to study plant behavior for the established phase, i.e., the long ...
A.K. Agrawal   +2 more
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, 2014
Sodium-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

Simulation of decay heat removal by active means following emergency shutdown in SFRs

Progress in nuclear energy (New series), 2023
G. Vikram   +3 more
semanticscholar   +1 more source

Research on decay heat removal effectiveness in pool-type fast reactor CEFR based on system code SAC-DRACS coupled with CFD software

Annals of Nuclear Energy, 2022
Jinsong Guo   +7 more
semanticscholar   +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

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