Results 1 to 10 of about 1,033,988 (155)

Numerical Simulations with RELAP5-3D and RELAP5/mod3.3 of the Second Experimental Campaign on In-Box LOCA Transients for HCLL TBS

open access: yesEnergies, 2021
In-box LOCA was identified as one of the worst accidental scenarios for the HCLL TBS (Helium Cooled Lithium-Lead Test Blanket System). Aiming to experimentally analyze the consequences of this transient, ENEA designed and built THALLIUM (Test HAmmer in ...
Alessandro Venturini   +2 more
exaly   +3 more sources

Development of a RELAP5/MOD3.3 Module for MHD Pressure Drop Analysis in Liquid Metals Loops: Verification and Validation

open access: yesEnergies, 2021
Magnetohydrodynamic (MHD) phenomena, due to the interaction between a magnetic field and a moving electro-conductive fluid, are crucial for the design of magnetic-confinement fusion reactors and, specifically, for the design of the breeding blanket ...
Lorenzo Melchiorri   +2 more
exaly   +3 more sources

Uncertainty Analysis of RELAP5-3D [PDF]

open access: yes, 2012
As world-wide energy consumption continues to increase, so does the demand for the use of alternative energy sources, such as Nuclear Energy. Nuclear Power Plants currently supply over 370 gigawatts of electricity, and more than 60 new nuclear reactors have been commissioned by 15 different countries.
Gertman, Alexandra E   +1 more
openaire   +3 more sources

Uncertainty Analysis for RELAP5-3D [PDF]

open access: yes, 2011
In its current state, RELAP5-3D is a 'best-estimate' code; it is one of our most reliable programs for modeling what occurs within reactor systems in transients from given initial conditions. This code, however, remains an estimator. A statistical analysis has been performed that begins to lay the foundation for a full uncertainty analysis.
Pawel, Aaron J., Mesina, Dr. George L.
openaire   +4 more sources

Development and application of multi-scale thermal fluid coupling program for molten salt cooled fast reactor based on RELAP5 and sub-channel program

open access: yesHe jishu, 2022
BackgroundThe natural circulation chloride cooled fast reactor (N3CFR) has the characteristics of simple structure, high inherent safety and good economy. It is an advanced fourth-generation nuclear energy system with development potential.
SONG Shiyang   +3 more
doaj   +1 more source

A mechanistic model of a PWR-based nuclear power plant in response to external hazard-induced station blackout accidents

open access: yesFrontiers in Energy Research, 2023
Natural hazard-induced nuclear accidents, such as the Fukushima Daiichi Accident that occurred in Japan in 2011, have significantly increased reactor safety studies in understanding nuclear power plant (NPP) responses to external hazard events such as ...
Tao Liu   +3 more
doaj   +1 more source

Application of best estimate plus uncertainty in review of research reactor safety analysis [PDF]

open access: yesNuclear Technology and Radiation Protection, 2015
To construct and operate a nuclear research reactor, the licensee is required to obtain the authorization from the regulatory body. One of the tasks of the regulatory authority is to verify that the safety analysis fulfils safety requirements ...
Adu Simon   +4 more
doaj   +1 more source

Best-Estimate for System Codes (BeSYC): A New Software to Perform Best-Estimate Plus Uncertainty Analyses with Thermal-Hydraulic and Safety System Codes for Both Fusion and Fission Scenarios

open access: yesApplied Sciences, 2021
The development and the validation of old and new software in relevant DEMO reactor conditions have been exploited in the latest years within the EUROfusion Consortium.
Bruno Gonfiotti   +6 more
doaj   +1 more source

Reactivity feedback effect on loss of flow accident in PWR

open access: yesNuclear Engineering and Technology, 2018
In this work, the reactor kinetics capability is used to compute the design safety parameters in a PWR due to complete loss of coolant flow during protected and unprotected accidents.
Basma Foad   +2 more
doaj   +1 more source

CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment

open access: yesNuclear Engineering and Technology, 2022
Multi-dimensional coupling analysis is a research hot spot in nuclear reactor thermal hydraulic study and both the full-scale system transient response and local key three-dimensional thermal hydraulic phenomenon could be obtained simultaneously, which ...
Linrong Ye   +6 more
doaj   +1 more source

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