Proceedings of the Sixteenth National Radio Science Conference. NRSC'99 (IEEE Cat. No.99EX249)
In thispaper, a software testing package using structural testing had been proposed and implement... more In thispaper, a software testing package using structural testing had been proposed and implemented. It can analyze any program written in C language. Moreover It can be applied to a wide spectrum C alike languages. C language had been chasen as an example for it. It makes two useful functions; one is a static analysis for the program under test and the other is a dynamic analysis for that program.
Early warning systems are critical in providing emergency response in the event of unexpected haz... more Early warning systems are critical in providing emergency response in the event of unexpected hazards. Cheap cameras and improvements in memory and computing power have enabled the design of fire detectors using video surveillance systems. This is critical in scenarios where traditional smoke detectors cannot be installed. In such scenarios, it has been observed that the smoke is visible well before flames can be sighted. This paper proposes a method to detect fire flame and/or smoke in real-time by processing the video data generated by ordinary camera monitoring a scene. The objective of this work is recognizing and modeling fire shape evolution in stochastic visual phenomenon. It focuses on detection of fire in image sequences by applying a hybrid algorithm that depends on optimizing the structure of a feed forward neural network. Fire detection experiments using various algorithms were carried. Results show that the proposed algorithm is very successful in detecting fire and/or smoke.
In a nuclear research reactors plant, a fault can occur in a few milliseconds, so locating the fa... more In a nuclear research reactors plant, a fault can occur in a few milliseconds, so locating the fault might be of utmost importance due to safety, and other important reasons. Accordingly, there is an increasing demand for automated systems to diagnose such failures. This paper proposes a new hybrid algorithm which considered as a novel method to detect faults in Egyptian research reactor in real-time. The new hybrid algorithm generates and processes many common faults by recognizing and modeling evolution in stochastic phenomenon. It focuses on detection of fault in data sequences by optimizing the backpropagation algorithm (BP), to determine the different common faults. Both differential evolution (DE) algorithms and neural networks, which are inspired by computation in biological systems, are emerged as established techniques for optimization and learning. So, this paper presents a software implementation of a neural network that had been optimized by Differential Evolution Algori...
Real time locating faults in any nuclear research reactors plants are the highest importance requ... more Real time locating faults in any nuclear research reactors plants are the highest importance requirements, aimed for safety of human and environmental reasons. Since a great fault can occur in a few milliseconds, accordingly, there is an increasing demand for automated systems to diagnose such failures. Adaptive Resonance network (ART) (1) is a neurofuzzy network, which is an important family of competitive neural learning model. Its memory mode is very similar to that of biological one, and memory capacitycan increase while the learning patterns increase. It can perform real-time online learning, and can work under non stationary world. In this research a new proposed a neural network classifier based on ART, which achieved preferable results than several other neural algorithms will be presented. The proposed algorithm obtains and diagnosis faults accidents patterns in the Multi- Purpose Research Reactor of Egypt, to avoid the risk of occurrence of a nuclear accident.
Fire safety in nuclear power plants (NPPs) is very important for realizing a high level of safety... more Fire safety in nuclear power plants (NPPs) is very important for realizing a high level of safety which investigate achievement reasonably protection for persons and the environment since fire can cause core melts thus emergency fire evacuations are concerned in NPPs. In this research, a new algorithm for Emergency fire evacuation is developed to minimize evacuation time for limiting the evacuee’s exposure to fire hazards products. The developed algorithm is a Safest Shortest Exit algorithm (SSE) which consists of three techniques: a rules-based to recognize the safest route, Distance Vector Hop (DV-Hop) localization to determine evacuee's location, and Dijkstra to produce the shortest route. The developed SSE is simulated for protecting the persons inside NPP buildings through three stages. Validation of the developed SSE algorithm is realised through simulation fire scenario inside a standard Main Control Room (MCR) in a Nuclear Power Plant as realistic fire scenario using the...
A system and method for improving microprocessor computer system out of order support via registe... more A system and method for improving microprocessor computer system out of order support via register management with synchronization of multiple pipelines and providing for processing a sequential stream of instructions in a computer system having a first and a second processing element, each of the processing elements having its own state determined by a setting of its own general purpose and control registers. When at any point in the processing of the sequential stream of instructions by the first processing element it becomes beneficial to have the second processing element begin continued processing of the same sequential instruction stream then the first and second processing elements process the sequential stream of instructions and may be executing the very same instruction but only one of said processing elements is permitted to change the overall architectural state of the computer system which is determined by a combination of the states of the first and second processing e...
Among the challenges that face wireless sensor network is minimizing the localization error and y... more Among the challenges that face wireless sensor network is minimizing the localization error and yet using minimum number of beacons. These two challenges are addressed in this pape by proposing a heuristic algorithm which is based on anchor based beacons and modified DV-Hop algorithm. The results give a recommended percentage of beacons that achieves a transmission accuracy of about 70%. The results are compared with similar algorithms and proven to be more general. The algorithm can be applied to detect the location of any anomalies inside the un-accessible rooms of the nuclear reactor which has high radiation levels, such as the mechanical control rods system room, while minimizing the power consumed.
Simulation of egress is vital for minimizing losses during fire disasters, however accurate simul... more Simulation of egress is vital for minimizing losses during fire disasters, however accurate simulations are scarce and real-life data is hard to come by. In this paper, a Proposed Wireless Fire Evacuation Model (PWFEM) is proposed to simulate fire evacuation process in a short time to minimize evacuee’s exposure to the harmful radiation and fire hazards. The PWFEM simulation realistic by supposing fire scenario at cabined contains electrical cables inside a standard Main Control Room (MCR) in a Nuclear Power Plant (NPP) building. In addition, a new Hybrid Safest Shortest Exit (HSSE) is developed which consists of three stages: safest route based on rules-based technique, evacuees location based on the DV-hop technique [1] and shortest route that depends on Dijkstra technique. The PWFEM Simulations are appreciated to yield a realistic fire scenario by using a telecommunications TCP/IP network in form of server and client sides that help in transfer data inside internal networks in th...
International Journal of Advances in Scientific Research and Engineering
This study involved mathematical modeling of turbine generator simulator (TGS) and speed governin... more This study involved mathematical modeling of turbine generator simulator (TGS) and speed governing system for Fast Breeder Reactor (FBR). All steam turbine system utilize governor controlled valves at the inlet to the turbine to control the steam flow. The previously developed FBR and Pressurized water reactors (PWR) mathematical models (by author) [1] were connected to the same Turbine-generator model and controlled by the same method of control. Then a comparison between the dynamic performance transient response of FBR and PWR controlled plants were considered in two cases, load demand perturbation and reactivity perturbations. The steam chest and inlet piping to the turbine cylinder introduce delays between valve movement and change in the steam flow. The results show that the model is capable of simulating the dynamic transient response for FBR in two cases, load demand perturbation and reactivity perturbations.
Article history: Received: 20th Jul. 2020 Accepted: 18th Mar. 2021 In this research, a new dynami... more Article history: Received: 20th Jul. 2020 Accepted: 18th Mar. 2021 In this research, a new dynamic model is developed for the IAEA 10 MW MTR as a research reactor. The developed dynamic model predicts the performance of the core design and the thermal hydraulic behavior in reactivity variations conditions for controlling startup conditions to reach criticality. The startup is performed by increasing or decreasing the reactivity due to insertion or withdrawal of a control rod with/without an external neutron source. The developed model is a dynamic model made by MATLAB/SIMULINK with a systematic solution of a combination of Ordinary Differential Equations (ODE) of Point Kinetic Equation (PKE) and the thermal hydraulic equations to calculate the change of neutron density, fuel and cooling temperatures through reaching the critical state before a new reactivity is added. The developed dynamic model predictions are compared with the calculations performed in various establishments using...
In this study a dynamic mathematical model is developed for the Intermediate heat exchanger (IHX)... more In this study a dynamic mathematical model is developed for the Intermediate heat exchanger (IHX) of a fast breeder reactor (FBR) in nuclear power plant (NPP).This model is connected to the previously developed FBR model (by author). In formulating the mathematical model for the IHX some assumptions are made. The IHX is simulated by one primary and one intermediate regions in the radial direction and two regions in the axial direction. The IHX simulator is described by a set of first order differential equations governing the mass, energy and momentum balance within FBR IHX system.
The ventilation and air cleaning system in the nuclear or radiological installations is one of th... more The ventilation and air cleaning system in the nuclear or radiological installations is one of the essential nuclear safety concerns. It is responsible for confining the radioactive materials involved behind suitable barriers during normal and abnormal conditions. It must be designed to prevent the release of harmful products (radioactive gases, or airborne radioactive materials) from the system or facility, impacting the public or workers, and doing environmental damage. There are two important safety functions common to all ventilation and air cleaning system in nuclear facilities. They are: a) the requirements to maintain the pressure of the ventilated volume below that of surrounding, relatively non-active areas, in order to inhibit the spread of contamination during normal and abnormal conditions, and b) the need to treat the ventilated gas so as to minimize the release of any radioactive or toxic materials. Keeping the two important safety functions is achieved by applying the...
A biometric hybrid algorithm is proposed for face recognition in real time. The algorithm first u... more A biometric hybrid algorithm is proposed for face recognition in real time. The algorithm first uses Huffman code compression to represent the image in a small size binary format. The binary vector is then fed as input to the First Adaptive Resonance Theory network, ART1, which is an unsupervised neural network, for image recognition. It is shown that the algorithm performs well on both live images and popular images databases. The algorithm is also compared with the performance of other face recognition algorithms as PCA and Eigen faces and the results prove that the proposed algorithm outperforms the other two algorithms. The extremely small recognition time of the algorithm makes it very suitable for use in emergency situations where recognition time is crucial as in case of fire occurrence in buildings which uses radiation materials or in nuclear power plants.
This study involved mathematical modeling of turbine generator simulator (TGS) and speed governin... more This study involved mathematical modeling of turbine generator simulator (TGS) and speed governing system for Fast Breeder Reactor (FBR). All steam turbine system utilize governor controlled valves at the inlet to the turbine to control the steam flow. The previously developed FBR and Pressurized water reactors (PWR) mathematical models (by author) [1] were connected to the same Turbine-generator model and controlled by the same method of control. Then a comparison between the dynamic performance transient response of FBR and PWR controlled plants were considered in two cases, load demand perturbation and reactivity perturbations. The steam chest and inlet piping to the turbine cylinder introduce delays between valve movement and change in the steam flow. The results show that the model is capable of simulating the dynamic transient response for FBR in two cases, load demand perturbation and reactivity perturbations.
In Nuclear Power Plants the Design Extension Conditions are more complex and severe than those po... more In Nuclear Power Plants the Design Extension Conditions are more complex and severe than those postulated as Design Basis Accidents, therefore, they must be taken into account in the safety analyses. In this study, many hypothetical investigated transients are applied on KONVOI pressurized water reactor during a 6-in. (182 cm2) cold leg Small Break Loss-of-Coolant-Accident to revise the effects of all safety systems ways through their availability/ nonavailability on the thermal hydraulic behaviour of the reactor. The investigated transients are represented through three cases of Small Break Loss-of-Coolant-Accident as, case-1, without scram and all of the safety systems are failure, case-2, the normal scram actuation with failure of all safety systems (nonavailability), and finally case 3, with normal actuation scram sequence and normal sequential actuation of all safety systems (availability). These three investigated transient cases are simulated by creation a model using Analysi...
International Journal of Computing and Network Technology
The relatively high dangerous thermal effects of electric cable in the Nuclear Power Plants (NPPs... more The relatively high dangerous thermal effects of electric cable in the Nuclear Power Plants (NPPs) is the concern to study the cable insulation behavior during a fire accident. This paper provides a comprehensive evaluation for the thermal failure in different cables types of the standard main control room (MCR) in nuclear power plants. Evaluation of the effective parameters is carried out using (CFAST) zone fire modeling. The fire growth in a MCR, is modeled and simulated to determine the effect of thermal failure temperatures corresponding to cable functional failures. This is to develop realistic single point thermal failure thresholds and probability distributions for specific cable insulation types.The output data are assessed for the different cable insulation materials according to the specific thermal failure thresholds, as well as to develop the electrical cable thermal fragility distributions. The present results show the cable functionality interdependence on the external firing.
Proceedings of the Sixteenth National Radio Science Conference. NRSC'99 (IEEE Cat. No.99EX249)
In thispaper, a software testing package using structural testing had been proposed and implement... more In thispaper, a software testing package using structural testing had been proposed and implemented. It can analyze any program written in C language. Moreover It can be applied to a wide spectrum C alike languages. C language had been chasen as an example for it. It makes two useful functions; one is a static analysis for the program under test and the other is a dynamic analysis for that program.
Early warning systems are critical in providing emergency response in the event of unexpected haz... more Early warning systems are critical in providing emergency response in the event of unexpected hazards. Cheap cameras and improvements in memory and computing power have enabled the design of fire detectors using video surveillance systems. This is critical in scenarios where traditional smoke detectors cannot be installed. In such scenarios, it has been observed that the smoke is visible well before flames can be sighted. This paper proposes a method to detect fire flame and/or smoke in real-time by processing the video data generated by ordinary camera monitoring a scene. The objective of this work is recognizing and modeling fire shape evolution in stochastic visual phenomenon. It focuses on detection of fire in image sequences by applying a hybrid algorithm that depends on optimizing the structure of a feed forward neural network. Fire detection experiments using various algorithms were carried. Results show that the proposed algorithm is very successful in detecting fire and/or smoke.
In a nuclear research reactors plant, a fault can occur in a few milliseconds, so locating the fa... more In a nuclear research reactors plant, a fault can occur in a few milliseconds, so locating the fault might be of utmost importance due to safety, and other important reasons. Accordingly, there is an increasing demand for automated systems to diagnose such failures. This paper proposes a new hybrid algorithm which considered as a novel method to detect faults in Egyptian research reactor in real-time. The new hybrid algorithm generates and processes many common faults by recognizing and modeling evolution in stochastic phenomenon. It focuses on detection of fault in data sequences by optimizing the backpropagation algorithm (BP), to determine the different common faults. Both differential evolution (DE) algorithms and neural networks, which are inspired by computation in biological systems, are emerged as established techniques for optimization and learning. So, this paper presents a software implementation of a neural network that had been optimized by Differential Evolution Algori...
Real time locating faults in any nuclear research reactors plants are the highest importance requ... more Real time locating faults in any nuclear research reactors plants are the highest importance requirements, aimed for safety of human and environmental reasons. Since a great fault can occur in a few milliseconds, accordingly, there is an increasing demand for automated systems to diagnose such failures. Adaptive Resonance network (ART) (1) is a neurofuzzy network, which is an important family of competitive neural learning model. Its memory mode is very similar to that of biological one, and memory capacitycan increase while the learning patterns increase. It can perform real-time online learning, and can work under non stationary world. In this research a new proposed a neural network classifier based on ART, which achieved preferable results than several other neural algorithms will be presented. The proposed algorithm obtains and diagnosis faults accidents patterns in the Multi- Purpose Research Reactor of Egypt, to avoid the risk of occurrence of a nuclear accident.
Fire safety in nuclear power plants (NPPs) is very important for realizing a high level of safety... more Fire safety in nuclear power plants (NPPs) is very important for realizing a high level of safety which investigate achievement reasonably protection for persons and the environment since fire can cause core melts thus emergency fire evacuations are concerned in NPPs. In this research, a new algorithm for Emergency fire evacuation is developed to minimize evacuation time for limiting the evacuee’s exposure to fire hazards products. The developed algorithm is a Safest Shortest Exit algorithm (SSE) which consists of three techniques: a rules-based to recognize the safest route, Distance Vector Hop (DV-Hop) localization to determine evacuee's location, and Dijkstra to produce the shortest route. The developed SSE is simulated for protecting the persons inside NPP buildings through three stages. Validation of the developed SSE algorithm is realised through simulation fire scenario inside a standard Main Control Room (MCR) in a Nuclear Power Plant as realistic fire scenario using the...
A system and method for improving microprocessor computer system out of order support via registe... more A system and method for improving microprocessor computer system out of order support via register management with synchronization of multiple pipelines and providing for processing a sequential stream of instructions in a computer system having a first and a second processing element, each of the processing elements having its own state determined by a setting of its own general purpose and control registers. When at any point in the processing of the sequential stream of instructions by the first processing element it becomes beneficial to have the second processing element begin continued processing of the same sequential instruction stream then the first and second processing elements process the sequential stream of instructions and may be executing the very same instruction but only one of said processing elements is permitted to change the overall architectural state of the computer system which is determined by a combination of the states of the first and second processing e...
Among the challenges that face wireless sensor network is minimizing the localization error and y... more Among the challenges that face wireless sensor network is minimizing the localization error and yet using minimum number of beacons. These two challenges are addressed in this pape by proposing a heuristic algorithm which is based on anchor based beacons and modified DV-Hop algorithm. The results give a recommended percentage of beacons that achieves a transmission accuracy of about 70%. The results are compared with similar algorithms and proven to be more general. The algorithm can be applied to detect the location of any anomalies inside the un-accessible rooms of the nuclear reactor which has high radiation levels, such as the mechanical control rods system room, while minimizing the power consumed.
Simulation of egress is vital for minimizing losses during fire disasters, however accurate simul... more Simulation of egress is vital for minimizing losses during fire disasters, however accurate simulations are scarce and real-life data is hard to come by. In this paper, a Proposed Wireless Fire Evacuation Model (PWFEM) is proposed to simulate fire evacuation process in a short time to minimize evacuee’s exposure to the harmful radiation and fire hazards. The PWFEM simulation realistic by supposing fire scenario at cabined contains electrical cables inside a standard Main Control Room (MCR) in a Nuclear Power Plant (NPP) building. In addition, a new Hybrid Safest Shortest Exit (HSSE) is developed which consists of three stages: safest route based on rules-based technique, evacuees location based on the DV-hop technique [1] and shortest route that depends on Dijkstra technique. The PWFEM Simulations are appreciated to yield a realistic fire scenario by using a telecommunications TCP/IP network in form of server and client sides that help in transfer data inside internal networks in th...
International Journal of Advances in Scientific Research and Engineering
This study involved mathematical modeling of turbine generator simulator (TGS) and speed governin... more This study involved mathematical modeling of turbine generator simulator (TGS) and speed governing system for Fast Breeder Reactor (FBR). All steam turbine system utilize governor controlled valves at the inlet to the turbine to control the steam flow. The previously developed FBR and Pressurized water reactors (PWR) mathematical models (by author) [1] were connected to the same Turbine-generator model and controlled by the same method of control. Then a comparison between the dynamic performance transient response of FBR and PWR controlled plants were considered in two cases, load demand perturbation and reactivity perturbations. The steam chest and inlet piping to the turbine cylinder introduce delays between valve movement and change in the steam flow. The results show that the model is capable of simulating the dynamic transient response for FBR in two cases, load demand perturbation and reactivity perturbations.
Article history: Received: 20th Jul. 2020 Accepted: 18th Mar. 2021 In this research, a new dynami... more Article history: Received: 20th Jul. 2020 Accepted: 18th Mar. 2021 In this research, a new dynamic model is developed for the IAEA 10 MW MTR as a research reactor. The developed dynamic model predicts the performance of the core design and the thermal hydraulic behavior in reactivity variations conditions for controlling startup conditions to reach criticality. The startup is performed by increasing or decreasing the reactivity due to insertion or withdrawal of a control rod with/without an external neutron source. The developed model is a dynamic model made by MATLAB/SIMULINK with a systematic solution of a combination of Ordinary Differential Equations (ODE) of Point Kinetic Equation (PKE) and the thermal hydraulic equations to calculate the change of neutron density, fuel and cooling temperatures through reaching the critical state before a new reactivity is added. The developed dynamic model predictions are compared with the calculations performed in various establishments using...
In this study a dynamic mathematical model is developed for the Intermediate heat exchanger (IHX)... more In this study a dynamic mathematical model is developed for the Intermediate heat exchanger (IHX) of a fast breeder reactor (FBR) in nuclear power plant (NPP).This model is connected to the previously developed FBR model (by author). In formulating the mathematical model for the IHX some assumptions are made. The IHX is simulated by one primary and one intermediate regions in the radial direction and two regions in the axial direction. The IHX simulator is described by a set of first order differential equations governing the mass, energy and momentum balance within FBR IHX system.
The ventilation and air cleaning system in the nuclear or radiological installations is one of th... more The ventilation and air cleaning system in the nuclear or radiological installations is one of the essential nuclear safety concerns. It is responsible for confining the radioactive materials involved behind suitable barriers during normal and abnormal conditions. It must be designed to prevent the release of harmful products (radioactive gases, or airborne radioactive materials) from the system or facility, impacting the public or workers, and doing environmental damage. There are two important safety functions common to all ventilation and air cleaning system in nuclear facilities. They are: a) the requirements to maintain the pressure of the ventilated volume below that of surrounding, relatively non-active areas, in order to inhibit the spread of contamination during normal and abnormal conditions, and b) the need to treat the ventilated gas so as to minimize the release of any radioactive or toxic materials. Keeping the two important safety functions is achieved by applying the...
A biometric hybrid algorithm is proposed for face recognition in real time. The algorithm first u... more A biometric hybrid algorithm is proposed for face recognition in real time. The algorithm first uses Huffman code compression to represent the image in a small size binary format. The binary vector is then fed as input to the First Adaptive Resonance Theory network, ART1, which is an unsupervised neural network, for image recognition. It is shown that the algorithm performs well on both live images and popular images databases. The algorithm is also compared with the performance of other face recognition algorithms as PCA and Eigen faces and the results prove that the proposed algorithm outperforms the other two algorithms. The extremely small recognition time of the algorithm makes it very suitable for use in emergency situations where recognition time is crucial as in case of fire occurrence in buildings which uses radiation materials or in nuclear power plants.
This study involved mathematical modeling of turbine generator simulator (TGS) and speed governin... more This study involved mathematical modeling of turbine generator simulator (TGS) and speed governing system for Fast Breeder Reactor (FBR). All steam turbine system utilize governor controlled valves at the inlet to the turbine to control the steam flow. The previously developed FBR and Pressurized water reactors (PWR) mathematical models (by author) [1] were connected to the same Turbine-generator model and controlled by the same method of control. Then a comparison between the dynamic performance transient response of FBR and PWR controlled plants were considered in two cases, load demand perturbation and reactivity perturbations. The steam chest and inlet piping to the turbine cylinder introduce delays between valve movement and change in the steam flow. The results show that the model is capable of simulating the dynamic transient response for FBR in two cases, load demand perturbation and reactivity perturbations.
In Nuclear Power Plants the Design Extension Conditions are more complex and severe than those po... more In Nuclear Power Plants the Design Extension Conditions are more complex and severe than those postulated as Design Basis Accidents, therefore, they must be taken into account in the safety analyses. In this study, many hypothetical investigated transients are applied on KONVOI pressurized water reactor during a 6-in. (182 cm2) cold leg Small Break Loss-of-Coolant-Accident to revise the effects of all safety systems ways through their availability/ nonavailability on the thermal hydraulic behaviour of the reactor. The investigated transients are represented through three cases of Small Break Loss-of-Coolant-Accident as, case-1, without scram and all of the safety systems are failure, case-2, the normal scram actuation with failure of all safety systems (nonavailability), and finally case 3, with normal actuation scram sequence and normal sequential actuation of all safety systems (availability). These three investigated transient cases are simulated by creation a model using Analysi...
International Journal of Computing and Network Technology
The relatively high dangerous thermal effects of electric cable in the Nuclear Power Plants (NPPs... more The relatively high dangerous thermal effects of electric cable in the Nuclear Power Plants (NPPs) is the concern to study the cable insulation behavior during a fire accident. This paper provides a comprehensive evaluation for the thermal failure in different cables types of the standard main control room (MCR) in nuclear power plants. Evaluation of the effective parameters is carried out using (CFAST) zone fire modeling. The fire growth in a MCR, is modeled and simulated to determine the effect of thermal failure temperatures corresponding to cable functional failures. This is to develop realistic single point thermal failure thresholds and probability distributions for specific cable insulation types.The output data are assessed for the different cable insulation materials according to the specific thermal failure thresholds, as well as to develop the electrical cable thermal fragility distributions. The present results show the cable functionality interdependence on the external firing.
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Papers by Dr Magy Kandil