Results 31 to 40 of about 105,023 (307)

CFD Analysis of Scaled Wire-wrapped rod Bundle Cooled by LBE [PDF]

open access: yesE3S Web of Conferences, 2019
Lead bismuth eutectic (LBE) is one of the most potential materials for coolant for Lead based reactor and Accelerator Driven Systems (ADS). Thermal-hydraulic behaviour of LBE in fuel assembly is a key issue for development of the systems. To get a deeper
LYU Kefeng   +3 more
doaj   +1 more source

Hydraulic-thermal decoupling simulation model for transient operation of natural gas pipeline networks

open access: yesYou-qi chuyun
ObjectiveThe transient operation simulation technology for natural gas pipeline networks is essential for peak shaving, economical and safe operation, and diagnosing abnormal service conditions.
Chunyu YU   +7 more
doaj   +1 more source

Oil pipeline hydraulic resistance coefficient identification

open access: yesCogent Engineering, 2021
The purpose of the study is to identify the hydraulic resistance coefficient of the main oil pipeline. Oil transportation through pipelines is the most efficient way to deliver oil from suppliers to consumers. The volume of transported oil depends on the
Timur Bekibayev   +3 more
doaj   +1 more source

Thermal-hydraulic analysis of a research reactor on personal computer with TARR code

open access: yesVietnam Journal of Mechanics, 1992
The code has been created for thermal-hydraulic calculation of stationary regime of nuclear research reactor, using personal computer. The main objective of the code is to compute the thermal parameters in the reactor core in order to avoid any accident.
Ngo Huy Can   +2 more
doaj   +1 more source

Simulation of rod ejection accident byPARCS code [PDF]

open access: yes, 2015
This paper describes reactor core model used for simulating REA. The model was designed in PARCS utilizing graphical interface SNAP. The data for model were given from benchmark NEACPR L-335.
Matějková, J.
core  

Nuclear and thermal hydraulic calculation of a representative I2S-LWR first core

open access: yesJournal of Energy : Energija, 2022
The Integral Inherently Safe Light Water Reactor (I2S-LWR) concept developed by Georgia Tech is a novel PWR reactor delivering electric power of 1000 MWe while implementing inherent safety features typical for Generation III+ small modular reactors. The main safety feature is based on integral primary circuit configuration, bringing together compact ...
Matijević, Mario   +3 more
openaire   +5 more sources

Interaction between Molten Al‐Killed Mn–B Steel and Carbon‐Bonded MgO Refractories Based on Recyclates

open access: yesAdvanced Engineering Materials, EarlyView.
High‐temperature interactions between low‐sulfur Al‐killed Mn–B steel and MgO–C refractories (0 and 50 wt% recyclates) are studied via finger immersion tests (1600 °C). Surface‐active elements influence infiltration. MgO/CaS layer forms, along with spinel and calcium silicate.
Matheus Roberto Bellé   +5 more
wiley   +1 more source

Extremal calculation problems of free convective movements in ventilated facades [PDF]

open access: yesИнженерно-строительный журнал, 2013
Systems of ventilated facades recently gain the increasing popularity. First of all it is explained by multifunctionality of these systems. Ventilated facades not only give the buildings expressive architectural shape, but also provide protection of the ...
D.V. Nemova   +2 more
doaj   +1 more source

Modeling of the heat balance of elements of a drill hydraulic remover for inject cementation of soils during operation [PDF]

open access: yesНаучно-технический вестник Брянского государственного университета, 2020
The article deals the issues of constructing by according to previously developed methods of the model that describes the heat balance in the unit “hydraulic puller-drill shaft”, which is used in jet-grouting devices. Two main groups of materials used in
Novikov V.I.   +2 more
doaj   +1 more source

DEMO WCLL BB breeding zone cooling system design: analysis and discussion [PDF]

open access: yes, 2019
The Water-Cooled Lithium-Lead (WCLL) Breeding Blanket (BB) is a key component in charge of ensuring Tritium self-sufficiency, shielding the Vacuum Vessel and removing the heat generated in the tokamak plasma.
Caruso, Gianfranco   +4 more
core   +1 more source

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