Download Experimental Nuclear Reactor Analysis Ebook PDF

Experimental Nuclear Reactor Analysis

Experimental Nuclear Reactor Analysis
Theory, Numerical Models and Experimental Analysis

by Antonio Cammi,Andrea Borio di Tigliole

  • Publisher : Woodhead Publishing
  • Release : 2021-06-15
  • Pages : 300
  • ISBN : 9780128185902
  • Language : En, Es, Fr & De
GET BOOK

Experimental Nuclear Reactor Analysis: Theory, Numerical Models and Experimental Analysis presents a consolidated resource on reactor analysis, comprising theoretical concepts of reactor physics, dynamics and thermal-hydraulics. Each element is applied to predict the behaviour of the TRIGA test reactor and its validation with the experimental data. Edited by Dr. Antonio Cammi and written by a team of expert contributors, this book is divided into three parts which provide the reader with a very thorough understanding of the different facets of nuclear reactor analysis. Part one presents various theoretical aspects which are required for the development of a computational model and experimental activities such as nuclear reactor physics, dynamics and control, and nuclear thermal hydraulics. The second part considers the concepts discussed in the first part, but applies them to develop computational tools for modelling the thermal-hydraulic and neutronic behaviour of reactors. The third part explores experiments designed to verify the results of computational models presented, along with a detailed description and analysis of the obtained results. This book serves as a complete guide to reactor analysis providing important theoretical background followed by a more advanced exploration and analysis of the experimental procedure and applications. Where readers do not have access to a test facility, the knowledge and practical understanding obtained from this book will ensure they are equipped with a very detailed insight and understanding of experimental reactor analysis, ready to apply to their own research and professional projects. Includes coverage of the computational models for the prediction of nuclear reactor neutronics and thermal-hydraulics Presents a description of experimental setup and procedure using TRIGA reactor and detailed analysis of obtained results and validation of computational predictions Contains exercises and applications throughout to deepen knowledge and understanding

Experimental Reactor Analysis and Radiation Measurements

Experimental Reactor Analysis and Radiation Measurements
A Book

by Donald D. Glower

  • Publisher : Unknown Publisher
  • Release : 1965
  • Pages : 348
  • ISBN : 9876543210XXX
  • Language : En, Es, Fr & De
GET BOOK

Physics of Nuclear Reactors

Physics of Nuclear Reactors
A Book

by P. Mohanakrishnan,Om Pal Singh,K. Umasankari

  • Publisher : Academic Press
  • Release : 2021-05-28
  • Pages : 786
  • ISBN : 0128224428
  • Language : En, Es, Fr & De
GET BOOK

Physics of Nuclear Reactors presents a comprehensive analysis of nuclear reactor physics. Editors P. Mohanakrishnan, Om Pal Singh, and Kannan Umasankari and a team of expert contributors combine their knowledge to guide the reader through a toolkit of methods for solving transport equations, understanding the physics of reactor design principles, and developing reactor safety strategies. The inclusion of experimental and operational reactor physics makes this a unique reference for those working and researching nuclear power and the fuel cycle in existing power generation sites and experimental facilities. The book also includes radiation physics, shielding techniques and an analysis of shield design, neutron monitoring and core operations. Those involved in the development and operation of nuclear reactors and the fuel cycle will gain a thorough understanding of all elements of nuclear reactor physics, thus enabling them to apply the analysis and solution methods provided to their own work and research. This book looks to future reactors in development and analyzes their status and challenges before providing possible worked-through solutions. Cover image: Kaiga Atomic Power Station Units 1 – 4, Karnataka, India. In 2018, Unit 1 of the Kaiga Station surpassed the world record of continuous operation, at 962 days. Image courtesy of DAE, India. Includes methods for solving neutron transport problems, nuclear cross-section data and solutions of transport theory Dedicates a chapter to reactor safety that covers mitigation, probabilistic safety assessment and uncertainty analysis Covers experimental and operational physics with details on noise analysis and failed fuel detection

Experimental Reactor Analysis Measurements

Experimental Reactor Analysis Measurements
A Book

by Donald Duane Glower

  • Publisher : Unknown Publisher
  • Release : 1965
  • Pages : 348
  • ISBN : 9876543210XXX
  • Language : En, Es, Fr & De
GET BOOK

Handbook of Nuclear Engineering

Handbook of Nuclear Engineering
Vol. 1: Nuclear Engineering Fundamentals; Vol. 2: Reactor Design; Vol. 3: Reactor Analysis; Vol. 4: Reactors of Generations III and IV; Vol. 5: Fuel Cycles, Decommissioning, Waste Disposal and Safeguards

by Dan Gabriel Cacuci

  • Publisher : Springer Science & Business Media
  • Release : 2010-09-14
  • Pages : 3574
  • ISBN : 0387981306
  • Language : En, Es, Fr & De
GET BOOK

This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.

Synthetic Experiment Design Technique in Reactor Analysis

Synthetic Experiment Design Technique in Reactor Analysis
A Book

by J. M. Krase

  • Publisher : Unknown Publisher
  • Release : 1956
  • Pages : 39
  • ISBN : 9876543210XXX
  • Language : En, Es, Fr & De
GET BOOK

Handbook of Nuclear Engineering

Handbook of Nuclear Engineering
Vol. 1: Nuclear Engineering Fundamentals; Vol. 2: Reactor Design; Vol. 3: Reactor Analysis; Vol. 4: Reactors of Generations III and IV; Vol. 5: Fuel Cycles, Decommissioning, Waste Disposal and Safeguards

by Dan Gabriel Cacuci

  • Publisher : Springer
  • Release : 2010-09-14
  • Pages : 3574
  • ISBN : 9780387981307
  • Language : En, Es, Fr & De
GET BOOK

The Handbook of Nuclear Engineering is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all academic levels, this five volume set provides the latest findings in nuclear data and experimental techniques, reactor physics, kinetics, dynamics and control. Readers will also find a detailed description of data assimilation, model validation and calibration, sensitivity and uncertainty analysis, fuel management and cycles, nuclear reactor types and radiation shielding. A discussion of radioactive waste disposal, safeguards and non-proliferation, and fuel processing with partitioning and transmutation is also included. As nuclear technology becomes an important resource of non-polluting sustainable energy in the future, The Handbook of Nuclear Engineering is an excellent reference for practicing engineers, researchers and professionals.

Proceedings of the ANPP Reactor Analysis Seminar, October 11 and 12, 1960

Proceedings of the ANPP Reactor Analysis Seminar, October 11 and 12, 1960
A Book

by J. F. O'Brien

  • Publisher : Unknown Publisher
  • Release : 1961
  • Pages : 294
  • ISBN : 9876543210XXX
  • Language : En, Es, Fr & De
GET BOOK

Experimental Stress Analysis in Fast Nuclear Reactor Safety

Experimental Stress Analysis in Fast Nuclear Reactor Safety
A Book

by S. Curioni,T. Trombetti

  • Publisher : Unknown Publisher
  • Release : 1978
  • Pages : 23
  • ISBN : 9876543210XXX
  • Language : En, Es, Fr & De
GET BOOK

Nuclear Power Plant Design and Analysis Codes

Nuclear Power Plant Design and Analysis Codes
Development, Validation, and Application

by Jun Wang,Xin Li,Chris Allison,Judy Hohorst

  • Publisher : Woodhead Publishing
  • Release : 2020-11-10
  • Pages : 608
  • ISBN : 0128181915
  • Language : En, Es, Fr & De
GET BOOK

Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe. Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs. Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting.

Experimental Analysis of Rossi-alpha and Noise Parameters in a Subcritical Nuclear Reactor

Experimental Analysis of Rossi-alpha and Noise Parameters in a Subcritical Nuclear Reactor
A Book

by David Taft Austin

  • Publisher : Unknown Publisher
  • Release : 1967
  • Pages : 154
  • ISBN : 9876543210XXX
  • Language : En, Es, Fr & De
GET BOOK

Accounting for Core Burnup in Reactor Analysis of the University of WIsconsin Nuclear Reactor

Accounting for Core Burnup in Reactor Analysis of the University of WIsconsin Nuclear Reactor
A Book

by Benjamin J. Schmitt

  • Publisher : Unknown Publisher
  • Release : 2006
  • Pages : 65
  • ISBN : 9876543210XXX
  • Language : En, Es, Fr & De
GET BOOK

The Use of Experimental Data in an MTR-type Nuclear Reactor Safety Analysis

The Use of Experimental Data in an MTR-type Nuclear Reactor Safety Analysis
A Book

by Simon E. Day

  • Publisher : Unknown Publisher
  • Release : 2006
  • Pages : 329
  • ISBN : 9780494203675
  • Language : En, Es, Fr & De
GET BOOK

The results are used to construct a practical safety analysis methodology for determining reactivity insertion safety limits for a light-water moderated and cooled MTR-type core.

Nuclear Data Needs for Generation IV Nuclear Energy Systems

Nuclear Data Needs for Generation IV Nuclear Energy Systems
Proceedings of the International Workshop, Antwerpen, Belgium, 5-7 April 2005

by P. Rullhusen

  • Publisher : World Scientific
  • Release : 2006
  • Pages : 286
  • ISBN : 9812773401
  • Language : En, Es, Fr & De
GET BOOK

This volume presents recent progress in the improvement of the nuclear database needed for the development of Generation IV nuclear energy systems. The Generation IV International Forum (GIF) identified six advanced concepts for sustainable nuclear energy production at competitive prices and with advanced safety, with special attention to nuclear non-proliferation and physical protection issues, minimization of long-lived radiotoxic waste, and optimum natural resource utilization System groups have been established for studying these concepts in detail, and nuclear data are an inherent part of these studies. This book reviews the work recently performed for the development of these systems. The contributions include an up-to-date overview of recent achievements in sensitivity analysis, model calculations, estimates of uncertainties, and the present status of nuclear databases with regard to their applications to Generation IV systems. In the workshop, special attention was given to the identification of nuclear data needs from sensitivity analysis of benchmark experiments and the treatment of uncertainties. The proceedings contain overviews of several experimental program and recent results of interest for the development of Generation IV systems. Contents: Nuclear Data Needs for Generation IV Systems: Future of Nuclear Energy and the Role of Nuclear Data (P Finck); Nuclear Data Needs for Generation IV Nuclear Energy Systems OCo Summary of US Workshop (T A Taiwo & H S Khalil); Innovative Fuel Types for Minor Actinides Transmutation (D Haas et al.); Benchmarks, Sensitivity Calculations, Uncertainties: Sensitivity of Advanced Reactor and Fuel Cycle Performance Parameters to Nuclear Data Uncertainties (G Aliberti et al.); Computer Model of an Error Propagation Through Micro-Campaign of Fast Neutron Gas Cooled Nuclear Reactor (E Ivanov); Generating Covariance Data with Nuclear Models (A J Koning); Experiments: INL Capabilities for Nuclear Data Measurements Using the Argonne Intense Pulsed Neutron Source Facility (J D Cole et al.); Cross-Section Measurements in the Fast Neutron Energy Range (A Plompen); Recent Measurements of Neutron Capture Cross Sections for Minor Actinides by an JNC and Kyoto University Group (H Harada et al.); Evaluated Data Libraries: Nuclear Data Evaluation for Generation IV (G Nogu re et al.); Improved Evaluations of Neutron-Induced Reactions on Americium Isotopes (P Talou et al.); and several other important contributions. Readership: Graduate students and nuclear physicists interested in experimental nuclear physics, nuclear reactions modeling, and reactor physics, especially the development of Generation IV reactors."

Activation Analysis

Activation Analysis
Cockcroft-Walton Generator Nuclear Reactor, LINAC, July 1966 Through June 1967

by James R. DeVoe

  • Publisher : Unknown Publisher
  • Release : 1967
  • Pages : 90
  • ISBN : 9876543210XXX
  • Language : En, Es, Fr & De
GET BOOK

Fractional-Order Models for Nuclear Reactor Analysis

Fractional-Order Models for Nuclear Reactor Analysis
A Book

by Gilberto Espinosa Paredes

  • Publisher : Woodhead Publishing
  • Release : 2020-10-27
  • Pages : 402
  • ISBN : 0128236663
  • Language : En, Es, Fr & De
GET BOOK

Fractional-Order Models for Nuclear Reactor Analysis presents fractional modeling issues in the context of anomalous diffusion processes in an accessible and practical way. The book emphasizes the importance of non-Fickian diffusion in heterogeneous systems as the core of the nuclear reactor, as well as different variations of diffusion processes in nuclear reactors which are presented to establish the importance of nuclear and thermohydraulic phenomena and the physical side effects of feedback. In addition, the book analyzes core issues in fractional modeling in nuclear reactors surrounding phenomenological description and important analytical sub-diffusive processes in the transport neutron. Users will find the most innovative modeling techniques of nuclear reactors using operator differentials of fractional order and applications in nuclear design and reactor dynamics. Proposed methods are tested with Boltzmann equations and non-linear order models alongside real data from nuclear power plants, making this a valuable resource for nuclear professionals, researchers and graduate students, as well as those working in nuclear research centers with expertise in mathematical modeling, physics and control. Presents and analyzes a new paradigm of nuclear reactor phenomena with fractional modeling Considers principles of fractional calculation, methods of solving differential equations of fractional order, and their applications Includes methodologies of linear and nonlinear analysis, along with design and dynamic analyses

Current Research in Nuclear Reactor Technology in Brazil and Worldwide

Current Research in Nuclear Reactor Technology in Brazil and Worldwide
A Book

by Amir Mesquita

  • Publisher : BoD – Books on Demand
  • Release : 2013-02-06
  • Pages : 346
  • ISBN : 9535109677
  • Language : En, Es, Fr & De
GET BOOK

The aim of this book is to disseminate state-of-the-art research and advances in the area of nuclear reactors technology. The book was divided in two parts.Topics discussed in the first part of this compilation include: experimental investigation and computational validation of thermal stratification in PWR reactors piping systems, new methods in doppler broadening function calculation for nuclear reactors fuel temperature, isothermal phase transformation of uranium-zirconium-niobium alloys for advanced nuclear fuel, reactivity Monte Carlo burnup simulations of enriched gadolinium burnable poison for PWR fuel, utilization of thermal analysis technique for study of uranium-molybdenum fuel alloy, probabilistic safety assessment applied to research reactors, and a review on the state-of-the art and current trends of next generation reactors. The second part includes: thermal hydraulics study for a ultra high temperature reactor with packed sphere fuels, benefits in using lead-208 coolant for fast reactors and accelerator driven systems, nuclear power as a basis for future electricity production in the world: Generation III and IV reactors, nanostructural materials and shaped solids for improvement and energetic effectiveness of nuclear reactors safety and radioactive wastes, multilateral nuclear approach to nuclear fuel cycles, and a cold analysis of the Fukushima accident.

Random Noise Techniques in Nuclear Reactor Systems

Random Noise Techniques in Nuclear Reactor Systems
A Book

by Robert E. Uhrig

  • Publisher : Unknown Publisher
  • Release : 1970
  • Pages : 490
  • ISBN : 9876543210XXX
  • Language : En, Es, Fr & De
GET BOOK

Analytical Chemistry in Nuclear Reactor Technology: Particle-size analysis

Analytical Chemistry in Nuclear Reactor Technology: Particle-size analysis
A Book

by Anonim

  • Publisher : Unknown Publisher
  • Release : 1959
  • Pages : 329
  • ISBN : 9876543210XXX
  • Language : En, Es, Fr & De
GET BOOK

Analytical and Experimental Investigation of a Nuclear Reactor Support Structure

Analytical and Experimental Investigation of a Nuclear Reactor Support Structure
A Book

by A. H. Marchertas,S. H. Fistedis,R. O. Brittan

  • Publisher : Unknown Publisher
  • Release : 1965
  • Pages : 100
  • ISBN : 9876543210XXX
  • Language : En, Es, Fr & De
GET BOOK

A general procedure is presented for determining the deformation (slopes and deflections) of a grid support structure for a nuclear reactor. Use is made of the Rayleigh-Ritz perturbation method which involves an infinite series of polynomials.