Author: B. Dubuisson
Publisher:
ISBN:
Category :
Languages : en
Pages : 96
Book Description
Fast Reactor Core Monitoring by Analysis of Temperature Noise
Author: B. Dubuisson
Publisher:
ISBN:
Category :
Languages : en
Pages : 96
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 96
Book Description
Fast Reactor Core Monitoring by Analysis of Temperature Noise
Author: B. Dubuisson
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Neutronics Methods for Transient and Safety Analysis of Fast Reactors
Author: Marchetti, Marco
Publisher: KIT Scientific Publishing
ISBN: 3731506114
Category :
Languages : en
Pages : 164
Book Description
Publisher: KIT Scientific Publishing
ISBN: 3731506114
Category :
Languages : en
Pages : 164
Book Description
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 488
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 488
Book Description
Noise Analysis in Nuclear Systems
Author:
Publisher:
ISBN:
Category : Noise control
Languages : en
Pages : 520
Book Description
Publisher:
ISBN:
Category : Noise control
Languages : en
Pages : 520
Book Description
Reactor Noise
Author: Joseph A. Thie
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 294
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 294
Book Description
The Large Core Code Evaluation Working Group Benchmark Analyses of a Homogeneous Fast Reactor
Author:
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 86
Book Description
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 86
Book Description
Progress in Nuclear Energy
Author: M. M. R. Williams
Publisher: Elsevier
ISBN: 1483103366
Category : Technology & Engineering
Languages : en
Pages : 297
Book Description
Progress in Nuclear Energy, Volume 5 covers the significant advances in several aspects of nuclear energy field. This book is composed six chapters that describe the progress in nuclear and gas-cooled reactors. The introductory chapter deals with the development and evolution of decay heat estimates and decay heat Standards, and illustrates the use of these estimates through comparison of both the actinide and fission product decay heat levels from typical fuel samples in a variety of reactor systems. The succeeding chapters present different practical methods for handling resonance absorption problem in the case of thermal reactor lattices and review the physics of the different noise phenomena. These topics are followed by discussions of the developed methodology for the description of breeding, conversion, long-term fuel logistics, and related subjects derived from the detailed mathematical description of the fuel cycle. The concluding chapters consider the historical development of heat transfer surfaces for gas-cooled reactors. These chapters also provide a complete set of differential nuclear data on the three technologically important americium isotopes, 241Am, 242Am, and 243Am, suitable for incorporation into the computer-based U.K. Nuclear Data Library. This book will prove useful to nuclear physicists and nuclear energy scientists and researchers.
Publisher: Elsevier
ISBN: 1483103366
Category : Technology & Engineering
Languages : en
Pages : 297
Book Description
Progress in Nuclear Energy, Volume 5 covers the significant advances in several aspects of nuclear energy field. This book is composed six chapters that describe the progress in nuclear and gas-cooled reactors. The introductory chapter deals with the development and evolution of decay heat estimates and decay heat Standards, and illustrates the use of these estimates through comparison of both the actinide and fission product decay heat levels from typical fuel samples in a variety of reactor systems. The succeeding chapters present different practical methods for handling resonance absorption problem in the case of thermal reactor lattices and review the physics of the different noise phenomena. These topics are followed by discussions of the developed methodology for the description of breeding, conversion, long-term fuel logistics, and related subjects derived from the detailed mathematical description of the fuel cycle. The concluding chapters consider the historical development of heat transfer surfaces for gas-cooled reactors. These chapters also provide a complete set of differential nuclear data on the three technologically important americium isotopes, 241Am, 242Am, and 243Am, suitable for incorporation into the computer-based U.K. Nuclear Data Library. This book will prove useful to nuclear physicists and nuclear energy scientists and researchers.
The Diagnostic Potential of Pattern Recognition Methods Applied to Temperature Noise Data from Simulated Fast Reactor Fuel Sub-assemblies
Author: B. Dubuisson
Publisher:
ISBN:
Category :
Languages : en
Pages : 65
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 65
Book Description
Temperature Noise Analysis and Sodium Boiling Detection in the Fuel Failure Mockup
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Sodium temperature noise was measured at the exit of simulated, fast-reactor fuel subassemblies in the Fuel Failure Mockup (FFM) to determine the feasibility of using temperature noise monitors to detect flow blockages in fast reactors. Also, acoustic noise was measured to determine whether sodium boiling in the FFM could be detected acoustically and whether noncondensable gas entrained in the sodium coolant would affect the sensitivity of the acoustic noise detection system. Information from these studies would be applied to the design of safety systems for operating liquid-metal fast breeder reactors (LMFBRs). It was determined that the statistical properties of temperature noise are dependent on the shape of temperature profiles across the subassemblies, and that a blockage upstream of a thermocouple that increases the gradient of the profile near the blockage will also increase the temperature noise at the thermocouple. Amplitude probability analysis of temperature noise shows a skewed amplitude density function about the mean temperature that varies with the location of the thermocouple with respect to the blockage location. It was concluded that sodium boiling in the FFM could be detected acoustically. However, entrained noncondensable gas in the sodium coolant at void fractions greater than 0.4 percent attenuated the acoustic signals sufficiently that boiling was not detected. At a void fraction of 0.1 percent, boiling was indicated only by the two acoustic detectors closest to the boiling site.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Sodium temperature noise was measured at the exit of simulated, fast-reactor fuel subassemblies in the Fuel Failure Mockup (FFM) to determine the feasibility of using temperature noise monitors to detect flow blockages in fast reactors. Also, acoustic noise was measured to determine whether sodium boiling in the FFM could be detected acoustically and whether noncondensable gas entrained in the sodium coolant would affect the sensitivity of the acoustic noise detection system. Information from these studies would be applied to the design of safety systems for operating liquid-metal fast breeder reactors (LMFBRs). It was determined that the statistical properties of temperature noise are dependent on the shape of temperature profiles across the subassemblies, and that a blockage upstream of a thermocouple that increases the gradient of the profile near the blockage will also increase the temperature noise at the thermocouple. Amplitude probability analysis of temperature noise shows a skewed amplitude density function about the mean temperature that varies with the location of the thermocouple with respect to the blockage location. It was concluded that sodium boiling in the FFM could be detected acoustically. However, entrained noncondensable gas in the sodium coolant at void fractions greater than 0.4 percent attenuated the acoustic signals sufficiently that boiling was not detected. At a void fraction of 0.1 percent, boiling was indicated only by the two acoustic detectors closest to the boiling site.