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Nuclear Material Performance

Nuclear Material Performance PDF Author: Rehab Abdel Rahman
Publisher: BoD – Books on Demand
ISBN: 9535124471
Category : Science
Languages : en
Pages : 174

Book Description
Assessing and improving nuclear material performance is a crucial subject for the sustainability of the nuclear energy and radioactive isotope supplies. This book aims to present research efforts used to identify nuclear materials performances in different areas. The contributions of esteemed international experts have covered important research aspects in fission and fusion technologies and naturally occurring radioactive materials management. The authors introduced current and anticipated trends toward better performances and mitigating challenges for commercial application of innovative technologies, biological remediation of mine effluents, nuclear fuel performance in power and research fission reactors, gamma ray spectrometer calibration, and recent advances in understanding the performance of tungsten composite in fusion reactor environment.

Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors

Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors PDF Author: National Academies of Sciences, Engineering, and Medicine
Publisher: National Academies Press
ISBN: 0309379210
Category : Science
Languages : en
Pages : 205

Book Description
The continued presence of highly enriched uranium (HEU) in civilian installations such as research reactors poses a threat to national and international security. Minimization, and ultimately elimination, of HEU in civilian research reactors worldwide has been a goal of U.S. policy and programs since 1978. Today, 74 civilian research reactors around the world, including 8 in the United States, use or are planning to use HEU fuel. Since the last National Academies of Sciences, Engineering, and Medicine report on this topic in 2009, 28 reactors have been either shut down or converted from HEU to low enriched uranium fuel. Despite this progress, the large number of remaining HEU-fueled reactors demonstrates that an HEU minimization program continues to be needed on a worldwide scale. Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors assesses the status of and progress toward eliminating the worldwide use of HEU fuel in civilian research and test reactors.

Nuclear Material Performance

Nuclear Material Performance PDF Author: Rehab Abdel Rahman
Publisher: BoD – Books on Demand
ISBN: 9535124471
Category : Science
Languages : en
Pages : 174

Book Description
Assessing and improving nuclear material performance is a crucial subject for the sustainability of the nuclear energy and radioactive isotope supplies. This book aims to present research efforts used to identify nuclear materials performances in different areas. The contributions of esteemed international experts have covered important research aspects in fission and fusion technologies and naturally occurring radioactive materials management. The authors introduced current and anticipated trends toward better performances and mitigating challenges for commercial application of innovative technologies, biological remediation of mine effluents, nuclear fuel performance in power and research fission reactors, gamma ray spectrometer calibration, and recent advances in understanding the performance of tungsten composite in fusion reactor environment.

Reactor Fuels, Materials and Systems under Extreme Environments

Reactor Fuels, Materials and Systems under Extreme Environments PDF Author: Wenzhong Zhou
Publisher: Frontiers Media SA
ISBN: 2889747662
Category : Technology & Engineering
Languages : en
Pages : 360

Book Description


Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors

Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201157201
Category : Technology & Engineering
Languages : en
Pages : 144

Book Description
This publication presents the material properties of all unirradiated Uranium-Molybdenum (U-Mo) fuel constituents that are essential for fuel designers and reactor operators to evaluate the fuel's performance and safety for research reactors. Many significant advances in the understanding and development of low enriched uranium U-Mo fuels have been made since 2004, stimulated by the need to understand irradiation behavior and early fuel failures during testing. The publication presents a comprehensive overview of mechanical and physical property data from U-Mo fuel research

Introduction to Surface Engineering

Introduction to Surface Engineering PDF Author: P. A. Dearnley
Publisher: Cambridge University Press
ISBN: 1316785084
Category : Technology & Engineering
Languages : en
Pages : 798

Book Description
This highly illustrated reference work covers the three principal types of surface technologies that best protect engineering devices and products: diffusion technologies, deposition technologies, and other less commonly acknowledged surface engineering (SE) techniques. Various applications are noted throughout the text and additionally whole chapters are devoted to specific SE applications across the automotive, gas turbine engine (GTE), metal machining, and biomedical implant sectors. Along with the benefits of SE, this volume also critically examines SE's limitations. Materials degradation pathways - those which can and those which cannot be mitigated by SE - are rigorously explained. Written from a scientific, materials engineering perspective, this concise text is supported by high-quality images and photo-micrographs which show how surfaces can be engineered to overcome the limits of conventionally produced materials, even in complex or hostile operating environments. This book is a useful resource for undergraduate and postgraduate students as well as professional engineers.

Diffusion in Materials DIMAT-2017

Diffusion in Materials DIMAT-2017 PDF Author: Eugen Rabkin
Publisher: Trans Tech Publications Ltd
ISBN: 3035731306
Category : Technology & Engineering
Languages : en
Pages : 205

Book Description
10th International Conference on Diffusion in Materials Selected, peer reviewed papers from the 10th International Conference on Diffusion in Materials (DIMAT-2017), Haifa, Israel, May 7-12, 2017.

Status of Fast Reactor Research and Technology Development

Status of Fast Reactor Research and Technology Development PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9781523130191
Category : Fast reactors
Languages : en
Pages : 0

Book Description
"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.

Medical Isotope Production Without Highly Enriched Uranium

Medical Isotope Production Without Highly Enriched Uranium PDF Author: National Research Council
Publisher: National Academies Press
ISBN: 0309130395
Category : Medical
Languages : en
Pages : 220

Book Description
This book is the product of a congressionally mandated study to examine the feasibility of eliminating the use of highly enriched uranium (HEU2) in reactor fuel, reactor targets, and medical isotope production facilities. The book focuses primarily on the use of HEU for the production of the medical isotope molybdenum-99 (Mo-99), whose decay product, technetium-99m3 (Tc-99m), is used in the majority of medical diagnostic imaging procedures in the United States, and secondarily on the use of HEU for research and test reactor fuel. The supply of Mo-99 in the U.S. is likely to be unreliable until newer production sources come online. The reliability of the current supply system is an important medical isotope concern; this book concludes that achieving a cost difference of less than 10 percent in facilities that will need to convert from HEU- to LEU-based Mo-99 production is much less important than is reliability of supply.

Advances in High Temperature Gas Cooled Reactor Fuel Technology

Advances in High Temperature Gas Cooled Reactor Fuel Technology PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201253101
Category : Business & Economics
Languages : en
Pages : 639

Book Description
This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

The Constitution Diagram of Molybdenum-rich Uranium-molybdenum Alloys

The Constitution Diagram of Molybdenum-rich Uranium-molybdenum Alloys PDF Author: Henry A. Saller
Publisher:
ISBN:
Category : Molybdenum alloys
Languages : en
Pages : 16

Book Description