Results 61 to 70 of about 1,865 (177)
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
Burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1 [PDF]
Nuclear Technology and Radiation Protection, 2011 The burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1, reference operating core, has been carried out utilizing standard computer codes WIMS/D4, CITATION, and RELAP5/MOD3.4.
Muhammad Atta +2 more
doaj +1 more source
MATHEMATICAL MODEL OF THE NPP KRŠKO PCFV SYSTEM FOR THE RELAP5 COMPUTER CODE
Journal of Energy : Energija, 2022 Containment building is the final barrier for radioactive releases from a nuclear power plant (NPP). Preserving its integrity will minimize these releases even in a case of a severe accident with core degradation and melt discharge in the containment accompanied with the pressure and temperature increase.
POŠTA, BORNA, SINIŠA, SINIŠA
openaire +4 more sources
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
SCDAP/RELAP5/MOD3 code development [PDF]
, 1992 The SCOAP/RELAP5/MOD3 computer code is designed to describe the overall reactor coolant system (RCS) thermal-hydraulic response, core damage progression, and fission product release and transport during severe accidents.
Siefken, J. L. +2 more
core
Numerical Analysis of the CIRCE-HERO PLOFA Scenarios
Applied Sciences, 2020 The present work deals with simulations carried out at the University of Pisa by using the System Thermal Hydraulics code RELAP5/Mod3.3 to support the experimental campaign conducted at the ENEA (Energia Nucleare ed Energie Alternative) Brasimone ...
Moscardini Marigrazia +4 more
doaj +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
Streamlining of the RELAP5-3D Code [PDF]
, 2007 RELAP5-3D is widely used by the nuclear community to simulate general thermal hydraulic systems and has proven to be so versatile that the spectrum of transient two-phase problems that can be analyzed has increased substantially over time. To accommodate
Hykes, Joshua +2 more
core
Mathematic preprocessor for RELAP5 code using Microsoft Excel
, 2006 O estudo termo-hidráulico, utilizado para análise de acidentes e transientes em reatores nucleares, é feito com o uso de algumas ferramentas computacionais sofisticadas.
Patricia Andrea Paladino Biaty +1 more
core +1 more source
Science and Technology of Nuclear Installations, 2015 In earlier study we have demonstrated that RELAP5 can predict flow instability parameters (flow rate, oscillation period, temperature, and pressure) in single channel tests in CIRCUS-IV facility. The main goals of this work are to (i) validate RELAP5 and
Viet-Anh Phung, Pavel Kudinov
doaj +1 more source