Results 71 to 80 of about 362 (143)
International Journal of Advanced Nuclear Reactor Design and Technology, 2020 Passive safety systems mostly working on the principles of natural circulation are given much priority in increasing the reliability of reactors’ inherent safety features.
Abbati Zahraddeen +4 more
doaj +1 more source
Code Development in Coupled PARCS/RELAP5 for Supercritical Water Reactor
Science and Technology of Nuclear Installations, 2014 The new capability is added to the existing coupled code package PARCS/RELAP5, in order to analyze SCWR design under supercritical pressure with the separated water coolant and moderator channels. This expansion is carried out on both codes.
Po Hu, Paul Wilson
doaj +1 more source
Atom Indonesia, 2019 In order to anticipate station blackout, the use of safety system based on passive features is highly considered in advanced nuclear power plant designs, especially after the Fukushima Dai-ichi nuclear power station accident.
A.R. Antariksawan +7 more
doaj +1 more source
Liquid metal cooled fast reactor thermal hydraulic research development: A review. [PDF]
Heliyon, 2023 Agbevanu KT +3 more
europepmc +1 more source
N Reactor RELAP5 model benchmark comparisons [PDF]
, 1988 This report documents work performed at the Idaho National Engineering Laboratory (INEL) in support of Westinghouse Hanford Company safety analyses for the N Reactor. The portion of the work reported here includes comparisons of RELAP5/MOD2-calculated data with measured plant data for: (1) a plant trip reactor transient from full power operation; and ...
Fletcher, C. D., Bolander, M. A.
openaire +2 more sources
Modeling Moving Systems with RELAP5-3D
Nuclear Science and Engineering, 2016 RELAP5-3D is typically used to model stationary, land-based reactors. However, it can also model reactors in other inertial and accelerating frames of reference. By changing the magnitude of the gravitational vector through user input, RELAP5-3D can model reactors on a space station or the moon.
G. L. Mesina +3 more
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Modifications to the VV PHTS RELAP5 Model [PDF]
, 2011 Modifications and improvements to a previous RELAP5 model of the Vacuum Vessel Primary Heat Transfer System are described in this report. The modifications were new pump models, a new steam pressurizer, new coolant water control systems, additional pipe structures, and reduction of the pulse power to 6 MW.
openaire +2 more sources
An Interpretable Time Series Data Prediction Framework for Severe Accidents in Nuclear Power Plants. [PDF]
Entropy (Basel), 2023 Fu Y, Zhang D, Xiao Y, Wang Z, Zhou H.
europepmc +1 more source
Simulation of Spray Injection in the Pressurizer Using RELAP5
Atom Indonesia, 2017 A modeling research using Relap5 to assess the pressurizer of a pressurized water reactor(PWR) power plant has been performed. The heater and water injection systems in the pressurizer system of the PWRare of greatimportance for system pressure control.The heater is designed to increase the pressure while the water sprayer injection is to perform ...
S. Dibyo, S Susyadi
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RELAP5/MOD3.3 Best Estimate Analyses for Human Reliability Analysis
Science and Technology of Nuclear Installations, 2010 To estimate the success criteria time windows of operator actions the conservative approach was used in the conventional probabilistic safety assessment (PSA). The current PSA standard recommends the use of best-estimate codes.
Andrej Prošek, Borut Mavko
doaj +1 more source