On the Development of the ISAAC Graphic Model

2006 ◽  
Author(s):  
K. R. Kim ◽  
S. D. Kim ◽  
Y. M. Song
Keyword(s):  
Reactor Core ◽  
Data Communication ◽  
System Structure ◽  
Graphical Display ◽  
Graphic Model ◽  
Severe Accidents ◽  
Basic Functions ◽  
Variable Definition ◽  
Control Capability ◽  
Communication Methods

Recently the development of graphical methods using the ISAAC code’s calculation data has been started in order to show the Wolsong 1 & 2 PHWR plants behaviour during the severe accidents. This graphic model is designed to provide two basic functions: one is to provide the graphical display of several plants systems together with the important parameters. For example, the representative T/H behaviour, fuel behaviour, fuel channel behaviour, reactor core behaviour, containment behaviour and fission product behaviour are going to be displayed in a graphic window. The other function is the control capability equipped with the controllable valves and pumps in the PHWR SAMG. In this paper, details of the elementary technical aspects of the ISAAC graphic model are presented which are the system structure, ISAAC variable definition, data communication methods and graphical display generation.

Invisible Dysontogenesis of X, Y, Z Generations (Transformation of Social Subjectivity Features)

2020 ◽  
Vol 144 ◽  
pp. 80-89
Author(s):  
Igor’ Yu. Sundiev ◽  
◽  
Andrey B. Frolov ◽  
Keyword(s):  
Normal Activity ◽  
System Structure ◽  
Resource Base ◽  
Social Functions ◽  
Terrorist Organizations ◽  
Deviant Behaviors ◽  
The Social ◽  
The Family ◽  
Basic Functions ◽  
And Control

The article analyzes the causes of population dysontogenesis-a hidden process of loss of human subjectivity: the destruction of its psychophysiological and psychosocial qualities necessary for the normal activity of society. Violations caused by unformed structures of the child’s brain during the period of socialization in the family and school are hardly noticeable in a state of comfort, but they manifest themselves under normative and especially peak psychophysiological loads: deviant behaviors, educational failure, deterioration of health and loss of reproductive functions. The consolidation of dysontogenesis in generations X, Y, and Z occurs through international educational standards that simplify educational programs and reduce didactic requirements to a level beyond which pathophenomenes become barely noticeable, but continue to accumulate statistically at the lower limit of the norm. Compensation for impaired functions occurs at the expense of modern means of digital communication-there is a non-specific “swarm” subjectivity: emotionally unstable, easily suggestible representatives of generations Y and Z become the main resource base of extremist and terrorist organizations. The loss of basic social functions of goal-setting and control, empathy and passionarity in generations X, Y, Z, a simplified view of reality, increased lability and network conformism, decreased libido, and redirection of creative energy to the virtual-all this leads to the cessation of reproduction of the properties of society as a system structure. Restoration of systemogenetic development is possible only if the basic functions of the social state — science, education and upbringing-are provided.

Experimental and Numerical Investigation of Solidification of Gallium in an Initially Emptied Horizontal Pipe Flow

2020 ◽  
Author(s):  
Shawn Somers-Neal ◽  
Alex Pegarkov ◽  
Edgar Matida ◽  
Vinh Tang ◽  
Tarik Kaya
Keyword(s):  
Numerical Model ◽  
Molten Metal ◽  
Reactor Core ◽  
Experimental Tests ◽  
Severe Accident ◽  
Penetration Length ◽  
Horizontal Pipe ◽  
Cooling Pipe ◽  
Severe Accidents ◽  
Core Meltdown

Abstract In a reactor core meltdown under postulated severe accidents, the molten material (corium) could be ejected or relocated through existing vessel penetrations (cooling pipe connections), thus potentially contaminating other locations in the power plant. There exists, however, a potential for plugging of melt flow due to its complete solidification, providing the availability of an adequate heat sink. Therefore, a numerical model was created to simulate the flow of molten metal through an initially empty horizontal pipe. The numerical model was verified using a previously developed analytical model and validated against experimental tests with gallium (low melting temperature) as a substitute for corium. The numerical model was able to predict the penetration length (length of distance travelled by the molten metal) after a complete blockage occurred with an average percent error range of 9%. Since the numerical model has been verified and validated, the model can be updated to predict the penetration length in the cooling pipe in case of a severe accident.

Analysis on Ex-Vessel Steam Explosion in CPR1000+ Unit

2010 ◽  
Author(s):  
Juanhua Zhang ◽  
Jiming Lin ◽  
Shishun Zhang
Keyword(s):  
Physical Model ◽  
Steam Explosion ◽  
Reactor Core ◽  
Reactor Vessel ◽  
Cavity Wall ◽  
Severe Accident ◽  
Severe Accidents ◽  
Structural Capacity ◽  
Impulse Load

Reactor Pit Flooding System (RPF) is adopted under the severe accidents situation in CPR1000+ units. It can move the heat generated from the reactor core via external reactor vessel cooling (ERVC) to keep the integrity of RPV and achieve the in-vessel corium retention (IVR). But if IVR function of RPF is failed, there is Ex-Vessel Steam Explosion (EX-SE) risk. The Ex-Vessel Steam Explosion is analyzed by MC3D software which is for fuel and cooling interaction (FCI). The physical model of CPR1000+ for Steam Explosion is built firstly and then the phenomenon of Ex-Vessel Steam Explosion under typical severe accident is analyzed. The conclusion of this study is that the impulse load of pressure on the cavity wall induced by steam explosion is about 310KPas ∼ 440KPas. Referencing the structure capacity of AP600 containment, if the structural capacity of CPR1000+ containment is equal to AP600, the impulse load of pressure is lower than it. So it could be preliminarily estimated that steam explosion will not threaten the integrality of CPR1000+ containment.

Web-Enabled Remote Control Laboratory Using an Embedded Ethernet Microcontroller

2012 ◽  
pp. 338-361 ◽  
Author(s):  
Chandresh Dubey ◽  
Hong Wong ◽  
Vikram Kapila ◽  
Parth Kumar
Keyword(s):  
Laboratory Experiments ◽  
Data Communication ◽  
Cost Effective ◽  
System Structure ◽  
Sensor Data ◽  
Control Panel ◽  
Communication Link ◽  
Control Laboratory ◽  
Runtime Environment ◽  
Online Laboratory

In this chapter, we report on the use of the TINI (Tiny InterNet Interface) microcontroller platform, DSTINIM400, as a cost effective solution to deploy feedback control laboratory experiments online. The DSTINIM400 has a built-in 10/100 Base-T Ethernet capability and provides 24 digital inputs/outputs. A TINI runtime environment, embedded in the DSTINIM400, allows developers to interact with the microcontroller like a network terminal where Java program code is downloaded and executed via the Ethernet communication protocol. The use of Java programming environment on the TINI microcontroller yields a simple interface to many Ethernet protocols allowing programmers to intuitively define a data communication link between the TINI microcontroller and a remote graphical user interface (GUI) control panel. We utilize the DSTINIM400 to interface with a variety of laboratory experiments, execute user-selectable control algorithms, and establish Internet data communication with remote GUI control panels. We provide remote GUI control panels in the form of Java applet webpages, where sensor data is presented to remote users as a plot GUI component and control system structure and parameter values are presented as binary switches, sliders, and text boxes. Finally, safety protocols are evaluated and implemented to safeguard online laboratory experiments.

Data communication and intelligence in traffic simulation environments: Simulation time and performance experiments

2021 ◽  
pp. 1-8
Author(s):  
Joonho Ko ◽  
Hyun Woong Cho ◽  
Jung In Kim ◽  
Hyunmyung Kim ◽  
Young-Joo Lee ◽  
...  
Keyword(s):  
Real Time ◽  
Traffic Simulation ◽  
Data Communication ◽  
Simulation Models ◽  
Traffic Information ◽  
Time Data ◽  
Simulation Performance ◽  
Communication Methods ◽  
Simulation Time ◽  
Simulation Environments

Transportation system management and traveler information systems evolve with the development of data communications and intelligence of traffic simulations. Variety of roadside and mobile sensing platforms will be deployed to allow communication between vehicles with Dedicated Short Range Communications (DSRC). Traffic data received from moving vehicles will be transmitted to each individual vehicle and traffic management center to provide real time traffic information. Microscopic traffic simulation models will be used for generating intelligence from real time data in the form of traffic analysis and prediction, since they have the highest detailed level of prediction such as vehicle / driver characteristics and have the capability to capture dynamically changing traffic conditions through the simulation. In this study, three communication methods for data communication and intelligence in traffic simulation environments are used including Ethernet, off-the-shelf wireless network, and one commercial network provider for data communication. Simulation time is measured and statistically analyzed using three different communication methods and one non-communication case. Also, traffic simulation performance is investigated to demonstrate the intelligence of traffic simulation tools in modeling traffic congestion.

Creation of Interface System for Nuclear Reactor Operation

2000 ◽  
Vol 44 (22) ◽  
pp. 571-574 ◽  
Author(s):  
Yukichi Yamaguchi ◽  
Fumiya Tanabe
Keyword(s):  
Nuclear Reactor ◽  
Empirical Evaluation ◽  
System Structure ◽  
Complex Nature ◽  
Graphical Display ◽  
Reactor Operation ◽  
Research Project ◽  
Interface System ◽  
Operation Procedure ◽  
System Verification

Present status of on going JAERI's research project aiming at empirical evaluation of the EID concept is described. The research project is proceeded with three consecutive steps: design and implementation of the interface system, verification, and validation of the interface on a full-scope reactor simulator. Following detailed analysis of system structure in a way of “walking-through” the operation procedure on the simulator, a new interface system was created on this. In the newly created interface system, sets of graphical display formats representing higher levels of information items and new navigation mechanism were introduced to cope with complex nature of reactor system. At present, verification work for this new interface system is being conducted.

Research on Train Control System Based on Communications

2012 ◽  
Vol 253-255 ◽  
pp. 1427-1430
Author(s):  
Lin Na He
Keyword(s):  
Communication Network ◽  
Control System ◽  
Communication Technology ◽  
Network Architecture ◽  
Open Data ◽  
Data Communication ◽  
System Structure ◽  
Train Control ◽  
Train Control System ◽  
Data Communication Network

This paper introduces communication based train contrl (CBTC) technology, focusing on the concept of the CBTC , the CBTC system structure, and the CBTC system basic principle. This paper presents the CBTC system is composed of two parts by the train control system and wireless information transmission, the CBTC system using wireless communication technology to achieve real-time bi-directional communication in the train and the trackside equipment, through an open data communication network. Finally, data communication subsystem network architecture in the CBTC system has been studied.

On Different Break Section of LOCA Cases

2017 ◽  
Author(s):  
Peiqi Liu ◽  
Tao Yu ◽  
Hongyan Yang
Keyword(s):  
Nuclear Power ◽  
Reactor Core ◽  
Severe Accident ◽  
Mitigation Measures ◽  
Good Time ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Primary Loop ◽  
Severe Accidents ◽  
Unit Model

A typical 1000MW pressurized-water reactor (PWR) unit model of China’s living nuclear power plant (NPP) units is built based on MAAP4[1] in this paper. Different severe accidents cases caused by different LOCA area on hot leg of primary loop are studied. And different mitigation measures are focused to evaluated their effectiveness. The study indicates that during the accident, the larger broken area LOCA case caused the more severe rector core damaged. However, it is important to inject water into the reactor core in good time. And that can mitigate the severe accident progress effectively.

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