Results 31 to 40 of about 90 (72)

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

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

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

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

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

Development of a computer code for thermal–hydraulic design and analysis of helically coiled tube once-through steam generator

open access: yesNuclear Engineering and Technology, 2017
The Helically coiled tube Once-Through Steam Generator (H-OTSG) is a key piece of equipment for compact small reactors. The present study developed and verified a thermal–hydraulic design and performance analysis computer code for a countercurrent H-OTSG
Yaoli Zhang   +3 more
doaj   +1 more source

Numerical Simulation of Flow Boiling in Small Channel of Plate OTSG

open access: yesFrontiers in Energy Research, 2020
The plate OTSG (once-through steam generator) with channel diameter of 1–3 mm has high volume-power ratio and powerful resistance to high temperature and high pressure.
Xiaofei Yuan   +9 more
doaj   +1 more source

Mathematical Modeling of Heat and Mass Transfer in Energy Science and Engineering 2014

open access: yes, 2015
Mathematical Problems in Engineering, Volume 2015, Issue 1, 2015.
Zhijun Zhang   +4 more
wiley   +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

Study on Thermal-hydraulic Steady-state Comprehensive Performance of Fast Reactor Sodium-water Steam Generator

open access: yesYuanzineng kexue jishu
The sodium-heated once-through steam generator (OTSG) plays an important role in separating the second and third circuits of sodium cooled fast reactor (SFR).
XIAO Changzhi1, YANG Hongyi1, ZHANG Dalin2, SHEN Geyu1, QIU Suizheng2, LU Yuan1, ZHANG Kui2, HUANG Yuanbin1
doaj   +1 more source

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