Results 51 to 60 of about 2,939 (182)
Implementation of DOWTHERM A Properties into RELAP5-3D/ATHENA [PDF]
, 2010 DOWTHERM A oil is being considered for use as a heat transfer fluid in experiments to help in the design of heat transfer components for the Next Generation Nuclear Plant (NGNP).
Moore, Richard L.
core +1 more source
International Journal of Energy Research, Volume 2025, Issue 1, 2025.This study presents a numerical modeling approach for analyzing the electrochemical and thermal–hydraulic characteristics of solid oxide electrolysis (SOE) cells and stacks for hydrogen production. A semilumped parameter‐based simulation code was developed and validated using experimental data and literature references.
Jiwon Ahn +3 more
wiley +1 more source
Analysis on Steady-State Operation and Heat Loss of Chinese Integrated Pressurized Water Reactor
Science and Technology of Nuclear Installations, 2014 Chinese integrated pressurized water reactor (CIPWR) has compact configuration and high inherent safety, which is appropriate for nuclear power plants of small and medium scale.
Zhang Fan +4 more
doaj +1 more source
International Journal of Energy Research, Volume 2025, Issue 1, 2025.Increased energy supply reliability, environmental sustainability, more competitive businesses, and improved standard of living are all made possible by more efficient energy conversion processes. In view of this, the present study aims at analysis and optimization of the operational parameters of a dual‐fuel‐fired boiler using Taguchi design method to
Sunday O. Oyedepo +5 more
wiley +1 more source
Bayesian Uncertainty Quantification of Reflooding Model With PSO–Kriging and PCA Approach
Science and Technology of Nuclear Installations, Volume 2025, Issue 1, 2025.To improve the process of best estimate plus uncertainty (BEPU) for nuclear safety assessment and calibration of thermal–hydraulic models for error reduction, inverse uncertainty quantification (IUQ) is proposed in recent years to quantify the uncertainty of model parameters in reactor program.
Ziyue Zhang +4 more
wiley +1 more source
Science and Technology of Nuclear Installations, 2017 This paper presents a faster solver named NRLU (Node Reordering Lower Upper) factorization solver to improve the solution speed for the pressure equations, which are formed by RELAP5/MOD3.3. The NRLU solver uses the oriented graph method and minimal fill-
Li Ge, Wei Liu, Jianqiang Shan
doaj +1 more source
Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model [PDF]
Journal of Applied and Computational Mechanics, 2017 Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the
Reza Akbari +2 more
doaj +1 more source
, 2001 The Reactor Excursion and Leak Analysis Program with 3D capability1 (RELAP5-3D) is a reactor system analysis code that has been developed at the Idaho National Engineering and Environmental Laboratory (INEEL) for the U. S. Department of Energy (DOE). The
Riemke, Richard Allan
core
International Journal of Energy Research, Volume 2024, Issue 1, 2024.In the case of multiple‐failure accidents in light water reactors, it is imperative to demonstrate that a significant fuel damage can be prevented via prearranged mitigation measures performed by operators. However, the time elapsed from the initiation of the event to the implementation of mitigation actions significantly influences the progress and ...
Jia Yu +3 more
wiley +1 more source
PaRaELAP: Realtime multiprocessing RELAP5 [PDF]
, 1991 An effort to parallelize RELAP5 was undertaken in order to capitalize on recent computational hardware developments in achieving the goal of realtime RELAP5 simulation.
Beelman, R.J.
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