Results 51 to 60 of about 695 (193)

Use of the Natural Circulation Flow Map for Natural Circulation Systems Evaluation

open access: yesScience and Technology of Nuclear Installations, Volume 2008, Issue 1, 2008., 2008
The aim of this paper is to collect and resume the work done to build and develop, at the University of Pisa, an engineering tool related to the natural circulation. After a brief description of the different loop flow regimes in single phase and two phase, the derivation of a suitable tool to judge the NC performance in a generic system is presented ...
M. Cherubini   +4 more
wiley   +1 more source

Experiencia del manejo de la obstrucción al tracto de salida gástrico de origen neoplásico en pacientes del Hospital Universitario San Ignacio (HUSI) en Bogotá, Colombia

open access: yesRevista de Gastroenterología de México, 2022
Resumen: Introducción: La obstrucción maligna al tracto de salida gástrico (OTSG) es una condición que altera la calidad de vida de los pacientes, condicionando un déficit nutricional con deterioro progresivo.
A.F. Ovalle-Hernández   +1 more
doaj   +1 more source

Study on physical prediction model of liquid film development and dry out point in helical tube

open access: yesFrontiers in Energy Research, 2023
Helical tubes are widely used in nuclear plants, heat recovery process, refrigeration technology, etc. It is obtained the helical tubes dry out point prediction model in accordance with the experimental conditions by numerical simulation.
Min Rui   +7 more
doaj   +1 more source

OTSG modeling for the analysis of the TMI incident [PDF]

open access: yes, 1980
The IRT code is a reactor plant systems code for the analysis of pressurized water reactor (PWR) transients that is being modified by Brookhaven National Laboratory for the Nuclear Regulatory Commission.
Shier, W. G., Hsu, C. J., Levine, M. M.
core  

Analytical methodology to estimate greenhouse gases (GHG) produced from OTSG steam generators in heavy oil field operations.

open access: yes, 2023
This degree work focuses its efforts on analyzing from an explanatory research methodology, taking as theoretical foundations the branches of thermodynamics and chemical reactions, to determine from mathematical analysis, the implications of greenhouse ...
Paredes Bernal, Julián David
core  

Enhancing hydraulic stability in once-through steam generators of small nuclear power plants: A novel approach using throttling baffles and feed pipes.

open access: yesJournal of Radiation Research and Applied Sciences, 2023
Given the increasing global interest in small nuclear power plants (SNPPs), the proposed research aims to investigate the design of once-through steam generators (OTSGs) used in SNPPs, with a particular focus on ensuring hydraulic stability in the heat ...
Xiaolong Zhou, Vladimir Kravchenko
doaj   +1 more source

Neutron measurements of the fuel remaining in the TMI II once-through steam generators (OTSG'S)

open access: yes, 1989
Polypropylene tubes containing a string of 18 copper rods were inserted into the lower head region and each J-leg of the two once-through steam generators (OTSG) of the unit two reactor at Three Mile Island.
Abel, K. H., Geelhood, B. D.
core   +1 more source

Model-Free Coordinated Control for MHTGR-Based Nuclear Steam Supply Systems

open access: yesEnergies, 2016
The modular high temperature gas-cooled reactor (MHTGR) is a typical small modular reactor (SMR) that offers simpler, standardized and safer modular design by being factory built, requiring smaller initial capital investment, and having a shorter ...
Zhe Dong
doaj   +1 more source

Conceptual Design of the Steam Generators for the EU DEMO WCLL Reactor

open access: yesEnergies, 2023
In the framework of the EUROfusion Horizon Europe Programme, ENEA and its linked third parties are in charge of the conceptual design of the steam generators belonging to EU DEMO WCLL Breeding Blanket Primary Heat Transfer Systems (BB PHTSs).
Amelia Tincani   +11 more
doaj   +1 more source

Numerical Simulation of an Out-Vessel Loss of Coolant from the Breeder Primary Loop Due to Large Rupture of Tubes in a Primary Heat Exchanger in the DEMO WCLL Concept

open access: yesEnergies, 2021
This work presents a thermohydraulic analysis of a postulated accident involving the rupture of the breeder primary cooling loop inside a heat exchanger (once through steam generator).
Francesco Galleni   +4 more
doaj   +1 more source

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