Author: OECD
Publisher: OECD Publishing
ISBN: 9789264181526
Category :
Languages : en
Pages : 296
Book Description
This conference proceedings shows how the core monitoring system can be used to support reactor operation in normal and anticipated transient modes and to supply data used to derive initial key core parameters for transient and accident analysis.
Core Monitoring for Commercial Reactors: Improvements in Systems and Methods Workshop Proceedings, Stockholm 4-5 October 1999
Reactor Core Monitoring
Author: Mihály Makai
Publisher: Springer
ISBN: 3319545760
Category : Technology & Engineering
Languages : en
Pages : 438
Book Description
This book presents a comprehensive overview of the computerized core monitoring techniques currently employed at pressurized water reactor (PWR) and boiling water reactor (BWR) nuclear power plants. It also offers a brief overview of the corresponding techniques at research and materials testing reactors. The book combines detailed descriptions of the theoretical background and fundamental underlying principles as well as the practical applications of core surveillance. It not only provides numerous industrial examples to illustrate how complex computerized systems are able to support the safe operation of nuclear reactors, but also outlines some new application areas that were made possible only by state-of-the-art computing resources. Thanks to its practical approach, it serves as a valuable and practical reference book for readers interested in the surveillance of nuclear reactors, ranging from undergraduate and postgraduate students to researchers and experts working at research reactors and nuclear power plants, as well as at nuclear regulatory authorities.
Publisher: Springer
ISBN: 3319545760
Category : Technology & Engineering
Languages : en
Pages : 438
Book Description
This book presents a comprehensive overview of the computerized core monitoring techniques currently employed at pressurized water reactor (PWR) and boiling water reactor (BWR) nuclear power plants. It also offers a brief overview of the corresponding techniques at research and materials testing reactors. The book combines detailed descriptions of the theoretical background and fundamental underlying principles as well as the practical applications of core surveillance. It not only provides numerous industrial examples to illustrate how complex computerized systems are able to support the safe operation of nuclear reactors, but also outlines some new application areas that were made possible only by state-of-the-art computing resources. Thanks to its practical approach, it serves as a valuable and practical reference book for readers interested in the surveillance of nuclear reactors, ranging from undergraduate and postgraduate students to researchers and experts working at research reactors and nuclear power plants, as well as at nuclear regulatory authorities.
Core Monitoring for Commercial Reactors: Improvements in Systems and Methods Workshop Proceedings, Stockholm 4-5 October 1999
Author: OECD
Publisher: OECD Publishing
ISBN: 9264181520
Category :
Languages : en
Pages : 296
Book Description
This conference proceedings shows how the core monitoring system can be used to support reactor operation in normal and anticipated transient modes and to supply data used to derive initial key core parameters for transient and accident analysis.
Publisher: OECD Publishing
ISBN: 9264181520
Category :
Languages : en
Pages : 296
Book Description
This conference proceedings shows how the core monitoring system can be used to support reactor operation in normal and anticipated transient modes and to supply data used to derive initial key core parameters for transient and accident analysis.
Proceedings of the Workshop on Core Monitoring for Commercial Reactors : Improvements in Systems and Methods
Author: OECD Nuclear Energy Agency
Publisher: OECD Publishing
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 302
Book Description
This conference proceedings shows how the core monitoring system can be used to support reactor operation in normal and anticipated transient modes and to supply data used to derive initial key core parameters for transient and accident analysis.
Publisher: OECD Publishing
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 302
Book Description
This conference proceedings shows how the core monitoring system can be used to support reactor operation in normal and anticipated transient modes and to supply data used to derive initial key core parameters for transient and accident analysis.
Proceedings of the Workshop on Core Monitoring for Commercial Reactors: Improvements in Systems and Methods
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 293
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 293
Book Description
Core Monitoring for Commercial Reactors
Author:
Publisher:
ISBN: 9789264176591
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN: 9789264176591
Category :
Languages : en
Pages : 0
Book Description
Characteristics and Performance Experience of Loose-part Monitoring Systems in U.S. Commercial Power Reactors
Author: R. C. Kryter
Publisher:
ISBN:
Category : Water cooled reactors
Languages : en
Pages : 40
Book Description
Publisher:
ISBN:
Category : Water cooled reactors
Languages : en
Pages : 40
Book Description
VERONA-plus
Author: F. Adorján
Publisher:
ISBN:
Category :
Languages : en
Pages : 10
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 10
Book Description
The Development of a Self-calibrating Power Monitoring System for Nuclear Reactors
Author: Mihaela Biro
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 214
Book Description
Abstract: The constant-temperature power sensor (CTPS) is a feedback-controlled calorimetric instrument capable of direct measurement of nuclear energy deposition. The CTPS simulates a section of the nuclear fuel element. The sensor operation is sensitive to the ambient coolant temperature and contact thermal resistance. The objective of this study is to develop a conceptual system for power measurements in the reactor core using such sensors. The monitoring system will process sensor signals from the reactor core in such a manner that probabilistic information, in the form of probability distribution function (pdf) of reactor power density is obtained at the sensor locations as well as between sensor locations. The desired pdfs of power density at sensor locations can be obtained by the implementation of the estimation algorithm DSD (Dynamic System Doctor). The DSD estimates the ambient coolant temperature and contact thermal resistance, information that is needed for correct evaluation of the local reactor power. Probability distribution functions of power density between sensor locations are obtained through interpolation methods. The software that constructs in real-time, three-dimensional core power distribution uses signals from an array of CTPSs distributed in the reactor core. Results are reported for an array of seven sensors distributed within a hypothetical reactor core, showing pdfs of power density well centered on the true value. The obtained results indicate that the estimation engine described in this study can be implemented in a computationally feasible manner to obtain probabilistic maps of power distribution in nuclear reactors under steady-state operation, as well as slow transients.
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 214
Book Description
Abstract: The constant-temperature power sensor (CTPS) is a feedback-controlled calorimetric instrument capable of direct measurement of nuclear energy deposition. The CTPS simulates a section of the nuclear fuel element. The sensor operation is sensitive to the ambient coolant temperature and contact thermal resistance. The objective of this study is to develop a conceptual system for power measurements in the reactor core using such sensors. The monitoring system will process sensor signals from the reactor core in such a manner that probabilistic information, in the form of probability distribution function (pdf) of reactor power density is obtained at the sensor locations as well as between sensor locations. The desired pdfs of power density at sensor locations can be obtained by the implementation of the estimation algorithm DSD (Dynamic System Doctor). The DSD estimates the ambient coolant temperature and contact thermal resistance, information that is needed for correct evaluation of the local reactor power. Probability distribution functions of power density between sensor locations are obtained through interpolation methods. The software that constructs in real-time, three-dimensional core power distribution uses signals from an array of CTPSs distributed in the reactor core. Results are reported for an array of seven sensors distributed within a hypothetical reactor core, showing pdfs of power density well centered on the true value. The obtained results indicate that the estimation engine described in this study can be implemented in a computationally feasible manner to obtain probabilistic maps of power distribution in nuclear reactors under steady-state operation, as well as slow transients.
Agent-based Structural Condition Monitoring for Nuclear Reactor Cores
Author: Gordon James Jahn
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A significant proportion of the UK energy needs are currently serviced by a fleet of ageing nuclear reactors. Ensuring that these reactors are operated safely is the highest priority and the structural health of their cores, that provide channels for control rods and coolant gas, is a key aspect. This thesis focuses on the application of structuralhealth monitoring to the graphite reactor cores used in the UK and presents a specification for the use of structural health monitoring (SHM) techniques already es- tablished in bridge and aircraft monitoring, with data obtained through existing reactor monitoring processes. This approach utilises statistical and clustering techniques on monitoring data that can be acquired during online operation of the plant. The use of existing monitoring processes to complement the established inspection regime for nuclear reactors is a novel contribution from this work. As part of proving the SHM approach, this thesis reports on work undertaken to identify suitable data and numerical limits for the cluster analysis. This analysis considers the data with respect to the stated aim of detectin~ core distortion and demonstrates that the chosen data and values are acceptable and conservative in the context of reactor condition monitoring. An assessment of the SHM solution is presented describing the im- plementation of the SHM approach using a multi-agent system (MAS), IMAPS. This implementation required consideration of using MAS tech- nology for condition monitoring, and the novel contribution of a technique for storing and retrieving historical data in a manner concomitant with both MAS and relational database theory is presented.ij The thesis concludes that condition monitoring is feasible on the graphite cores, and that multi-variate analysis through SHM implemented within a MAS offers a storage and analysis platform that can both handle the data volumes and accommodate further extensions as required.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A significant proportion of the UK energy needs are currently serviced by a fleet of ageing nuclear reactors. Ensuring that these reactors are operated safely is the highest priority and the structural health of their cores, that provide channels for control rods and coolant gas, is a key aspect. This thesis focuses on the application of structuralhealth monitoring to the graphite reactor cores used in the UK and presents a specification for the use of structural health monitoring (SHM) techniques already es- tablished in bridge and aircraft monitoring, with data obtained through existing reactor monitoring processes. This approach utilises statistical and clustering techniques on monitoring data that can be acquired during online operation of the plant. The use of existing monitoring processes to complement the established inspection regime for nuclear reactors is a novel contribution from this work. As part of proving the SHM approach, this thesis reports on work undertaken to identify suitable data and numerical limits for the cluster analysis. This analysis considers the data with respect to the stated aim of detectin~ core distortion and demonstrates that the chosen data and values are acceptable and conservative in the context of reactor condition monitoring. An assessment of the SHM solution is presented describing the im- plementation of the SHM approach using a multi-agent system (MAS), IMAPS. This implementation required consideration of using MAS tech- nology for condition monitoring, and the novel contribution of a technique for storing and retrieving historical data in a manner concomitant with both MAS and relational database theory is presented.ij The thesis concludes that condition monitoring is feasible on the graphite cores, and that multi-variate analysis through SHM implemented within a MAS offers a storage and analysis platform that can both handle the data volumes and accommodate further extensions as required.