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Science and Technology of Nuclear Installations, Volume 2026, Issue 1, 2026.Sodium‐cooled fast reactor (SFR) is one of the fourth‐generation nuclear reactor types, which has inherent safety features such as low corrosion and no severe interaction between molten fuel and sodium. However, the severe accident of core melting in SFR needs to be considered.
Yingying Huo +3 more
wiley +1 more source
SCDAP/RELAP5/MOD2 Code Manual [PDF]
, 1989 The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, and the fission products and ...
Hagrman, D. L. +14 more
core +1 more source
SCDAP/RELAP5 independent peer review [PDF]
, 1993 The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light-water-reactor coolant systems during severe accidents. The newest version of the code is SCDAP/RELAP5/MOD3.
Jenks, R.P. (Los Alamos National Lab., NM (United States)) +5 more
core +3 more sources
Science and Technology of Nuclear Installations, 2016 The latest versions of RELAP5-3D© code allow the simulation of thermodynamic system, using different type of working fluids, that is, liquid metals, molten salt, diathermic oil, and so forth, thanks to the ATHENA code integration.
P. Balestra +3 more
doaj +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
APPLICATION OF MCNP FOR PREDICTING POWER EXCURSION DURING LOCA IN ATUCHA-2 PHWR [PDF]
, 2012 This thesis consists in the developing and application of a methodology based on MCNP code to predict power and reactivity excursions depending on different representation of physical variables.
PECCHIA, MARCO
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
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
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
Recent Applications of RELAP5-3D at GRNSPG [PDF]
, 2012 CNA2 : FSAR activities Standard Consolidated Reference Experimental Database MASLWR benchmark OECD benchmarks CHF calculation in low mass flux condition Turbulence effects in Relap5 ...
Veronese, F. +9 more
core