Results 41 to 50 of about 695 (193)

A Differential‐Algebraic Model for the Once‐Through Steam Generator of MHTGR‐Based Multimodular Nuclear Plants

open access: yesMathematical Problems in Engineering, Volume 2015, Issue 1, 2015., 2015
Small modular reactors (SMRs) are those fission reactors whose electrical output power is no more than 300 MWe. SMRs usually have the inherent safety feature that can be applicable to power plants of any desired power rating by applying the multimodular operation scheme. Due to its strong inherent safety feature, the modular high temperature gas‐cooled
Zhe Dong, Zhijun Zhang
wiley   +1 more source

Evaluation of single heated channel and subchannel modelling on a nuclear once through steam generator (OTSG)

open access: yes
Steam generator is one of the most important components of pressurized-water reactor. This component plays the role of heat transfer and pressure boundary between primary and secondary side fluids.
Shirani, A.S.   +2 more
core   +6 more sources

A Novel Fractional‐Order PID Controller for Integrated Pressurized Water Reactor Based on Wavelet Kernel Neural Network Algorithm

open access: yesMathematical Problems in Engineering, Volume 2014, Issue 1, 2014., 2014
This paper presents a novel wavelet kernel neural network (WKNN) with wavelet kernel function. It is applicable in online learning with adaptive parameters and is applied on parameters tuning of fractional‐order PID (FOPID) controller, which could handle time delay problem of the complex control system.
Yu-xin Zhao   +3 more
wiley   +1 more source

ICONE2011-43178 Analysis of the oscillation among channels of OTSG in movable nuclear power devices

open access: yesThe Proceedings of the International Conference on Nuclear Engineering (ICONE), 2011
HOU, Su-xia   +4 more
exaly   +2 more sources

Modelling and Dynamic Behaviour Analysis of the Steam Supply System for Double-Reactor and Multi-Turbine Nuclear Power Plant

open access: yesChemical Engineering Transactions, 2019
This paper proposes a first principle dynamic model of the Nuclear Steam Supply System (NSSS) for the Double-Reactor and Multi-Turbine Nuclear Power Plant (DMNPP).
Chengcheng Cui   +4 more
doaj   +1 more source

Experimental study on helical tubes heat transfer characteristics considering corrosion products

open access: yesFrontiers in Energy Research, 2023
During the power operation of nuclear reactors, the corrosion products in the secondary circuit will deposit on the inside of Helical-coiled One-Through Steam Generator (H-OTSG) heat transfer tubes and form fouling.
Mao Yulong   +8 more
doaj   +1 more source

Analysis on Steady‐State Operation and Heat Loss of Chinese Integrated Pressurized Water Reactor

open access: yesScience and Technology of Nuclear Installations, Volume 2014, Issue 1, 2014., 2014
Chinese integrated pressurized water reactor (CIPWR) has compact configuration and high inherent safety, which is appropriate for nuclear power plants of small and medium scale. Heat balance model has been adopted widely in thermal power calibration of PWRs because of its advantage of accuracy.
Zhang Fan   +5 more
wiley   +1 more source

Numerical simulation of corrosion product particle deposition in once-through steam generators [PDF]

open access: yesEPJ Web of Conferences
The Once-Through Steam Generator (OTSG), characterized by its compact design and superior heat transfer efficiency, presents complex flow dynamics that influence particle deposition.
Cao Chengque, Li Huaibin
doaj   +1 more source

Experience in the management of neoplastic gastric outlet obstruction in patients at the Hospital Universitario San Ignacio in Bogotá, Colombia

open access: yesRevista de Gastroenterología de México (English Edition), 2022
Introduction: Malignant gastric outlet obstruction is a condition that alters patient quality of life, conditioning progressive malnutrition. However, self-expanding metal stents (SEMSs) and surgical gastrojejunostomy (SGJ) are palliative options in ...
A.F. Ovalle-Hernández   +1 more
doaj   +1 more source

Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor

open access: yesScience and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009
A theoretical investigation on the thermal hydraulic characteristics of a new type of passive residual heat removal system (PRHRS), which is connected to the reactor coolant system via the secondary side of the steam generator, for an integral pressurized water reactor is presented in this paper.
Junli Gou   +4 more
wiley   +1 more source

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