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Validation Of The Physics Analysis Used To Characterize The Agr 1 Triso Fuel Irradiation Test
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Book Synopsis Validation of the Physics Analysis Used to Characterize the AGR-1 TRISO Fuel Irradiation Test by :
Download or read book Validation of the Physics Analysis Used to Characterize the AGR-1 TRISO Fuel Irradiation Test written by and published by . This book was released on 2015 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: The results of a detailed physics depletion calculation used to characterize the AGR-1 TRISO-coated particle fuel test irradiated in the Advanced Test Reactor (ATR) at the Idaho National Laboratory are compared to measured data for the purpose of validation. The particle fuel was irradiated for 13 ATR power cycles over three calendar years. The physics analysis predicts compact burnups ranging from 11.30-19.56% FIMA and cumulative neutron fast fluence from 2.21?4.39E+25 n/m2 under simulated high-temperature gas-cooled reactor conditions in the ATR. The physics depletion calculation can provide a full characterization of all 72 irradiated TRISO-coated particle compacts during and post-irradiation, so validation of this physics calculation was a top priority. The validation of the physics analysis was done through comparisons with available measured experimental data which included: 1) high-resolution gamma scans for compact activity and burnup, 2) mass spectrometry for compact burnup, 3) flux wires for cumulative fast fluence, and 4) mass spectrometry for individual actinide and fission product concentrations. The measured data are generally in very good agreement with the calculated results, and therefore provide an adequate validation of the physics analysis and the results used to characterize the irradiated AGR-1 TRISO fuel.
Book Synopsis Advances in High Temperature Gas Cooled Reactor Fuel Technology by : International Atomic Energy Agency
Download or read book Advances in High Temperature Gas Cooled Reactor Fuel Technology written by International Atomic Energy Agency and published by . This book was released on 2012-06 with total page 639 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Thermal and Flow Design of Helium-cooled Reactors by : Gilbert Melese
Download or read book Thermal and Flow Design of Helium-cooled Reactors written by Gilbert Melese and published by . This book was released on 1984 with total page 444 pages. Available in PDF, EPUB and Kindle. Book excerpt: This source book provides both an overview of gas-cooled reactors and a detailed look at the high-temperature gas-cooled reactor (HTGR). Taking a worldwide perspective, this book reviews the early development of the HTGR and explores potential future development and applications.
Book Synopsis Fission Product Processes In Reactor Accidents by : J. T. Rogers
Download or read book Fission Product Processes In Reactor Accidents written by J. T. Rogers and published by CRC Press. This book was released on 2020-12-17 with total page 883 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.
Book Synopsis Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor by : Willem Frederik Geert van Rooijen
Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by IOS Press. This book was released on 2006 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
Book Synopsis Optimized Core Design and Fuel Management of a Pebble-bed Type Nuclear Reactor by : Brian Boer
Download or read book Optimized Core Design and Fuel Management of a Pebble-bed Type Nuclear Reactor written by Brian Boer and published by . This book was released on 2008 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Very High Temperature Reactor (VHTR) has been selected by the international Generation IV research initiative as one of the six most promising nuclear reactor concepts that are expected to enter service in the second half of the 21st century. As one of the fourth generation nuclear reactors, the VHTR is characterized by high plant efficiency and a high fuel discharge burn-up level. More specifically, the (pebble-bed type) High Temperature Reactor (HTR) is known for its inherently safe characteristics, coming from a negative temperature reactivity feedback, a low power density and a large thermal inertia of the core.
Book Synopsis Complex Concentrated Alloys (CCAs) by : Sundeep Mukherjee
Download or read book Complex Concentrated Alloys (CCAs) written by Sundeep Mukherjee and published by MDPI. This book was released on 2020-11-04 with total page 278 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is a collection of several unique articles on the current state of research on complex concentrated alloys, as well as their compelling future opportunities in wide ranging applications. Complex concentrated alloys consist of multiple principal elements and represent a new paradigm in structural alloy design. They show a range of exceptional properties that are unachievable in conventional alloys, including high strength–ductility combination, resistance to oxidation, corrosion/wear resistance, and excellent high-temperature properties. The research articles, reviews, and perspectives are intended to provide a wholistic view of this multidisciplinary subject of interest to scientists and engineers.
Book Synopsis Physics of High-Temperature Reactors by : Luigi Massimo
Download or read book Physics of High-Temperature Reactors written by Luigi Massimo and published by Elsevier. This book was released on 2013-10-22 with total page 249 pages. Available in PDF, EPUB and Kindle. Book excerpt: Physics of High-Temperature Reactors focuses on the physics of high-temperature reactors (HTRs) and covers topics ranging from fuel cycles and refueling strategies to neutron cross-sections, transport and diffusion theory, and resonance absorption. Spectrum calculations and cross-section averaging are also discussed, along with the temperature coefficient and reactor control. Comprised of 16 chapters, this book begins with a general description of the HTR core as well as its performance limitations. The next chapter deals with general considerations about HTR physics, including quantities to be determined and optimized in the design of nuclear reactors. Potential scattering and resonance reactions between neutrons and atomic nuclei are then considered, together with basic aspects of transport and diffusion theory. Subsequent chapters explore methods for solving the diffusion equation; slowing-down and neutron thermalization in graphite; HTR core design, fuel management, and cost calculations; and core dynamics and accident analysis. The final chapter describes the sequence of reactor design calculations. This monograph is written primarily for students of HTR physics who are preparing to enter the field as well as technologists of other disciplines who are working on the system.
Book Synopsis Management of Nuclear Power Plant Projects by : IAEA
Download or read book Management of Nuclear Power Plant Projects written by IAEA and published by International Atomic Energy Agency. This book was released on 2020-11-25 with total page 221 pages. Available in PDF, EPUB and Kindle. Book excerpt: Member States intending to introduce a nuclear power programme will need to pass through several phases during the implementation. Experience shows that careful planning of the objectives, roles, responsibilities, interfaces and tasks to be carried out in different phases of a nuclear project is important for success. This publication presents a harmonized approach that may be used to structure the owner/operator management system and establish and manage nuclear projects and their development activities irrespective of the adopted approach. It has been developed from shared management practices and consolidated experiences provided by nuclear project management specialists through a series of workshops and working groups organized by the IAEA. The resultant publication presents a useful framework for the management of nuclear projects from initiation to closeout and captures international best practices.
Author :International Atomic Energy Agency Publisher :IAEA Tecdoc Series No. 1790 ISBN 13 :9789201040169 Total Pages :0 pages Book Rating :4.0/5 (41 download)
Book Synopsis Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal by : International Atomic Energy Agency
Download or read book Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal written by International Atomic Energy Agency and published by IAEA Tecdoc Series No. 1790. This book was released on 2016 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal.
Book Synopsis Status of and Prospects for Gas-cooled Reactors by : International Atomic Energy Agency
Download or read book Status of and Prospects for Gas-cooled Reactors written by International Atomic Energy Agency and published by . This book was released on 1984 with total page 294 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Statute of the International Atomic Energy Agency by : United States. Congress. Senate. Committee on Foreign Relations
Download or read book Statute of the International Atomic Energy Agency written by United States. Congress. Senate. Committee on Foreign Relations and published by . This book was released on 1957 with total page 274 pages. Available in PDF, EPUB and Kindle. Book excerpt: Considers ratification of an international agreement to establish the International Atomic Energy Agency.
Book Synopsis Nuclear Power Plant Design and Analysis Codes by : Jun Wang
Download or read book Nuclear Power Plant Design and Analysis Codes written by Jun Wang and published by Woodhead Publishing. This book was released on 2020-11-10 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
Book Synopsis Reactor Development by : Lyle B. Borst
Download or read book Reactor Development written by Lyle B. Borst and published by . This book was released on 1948 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Application of Compact Heat Exchangers For Combined Cycle Driven Efficiency In Next Generation Nuclear Power Plants by : Bahman Zohuri
Download or read book Application of Compact Heat Exchangers For Combined Cycle Driven Efficiency In Next Generation Nuclear Power Plants written by Bahman Zohuri and published by Springer. This book was released on 2015-11-19 with total page 379 pages. Available in PDF, EPUB and Kindle. Book excerpt: Covers the fundamentals of combined-cycle plants to provide background for understanding the progressive design approaches at the heart of the text Discusses the types of compact heat exchanger surfaces, suggesting novel designs that can be considered for optimal cost effectiveness and maximum energy production Undertakes the thermal analysis of these compact heat exchangers throughout the life cycle, from the design perspective through operational and safety assurance stages This book describes the quest to create novel designs for compact heat exchangers in support of emergent combined cycle nuclear plants. The text opens with a concise explanation of the fundamentals of combined cycles, describing their efficiency impacts on electrical power generation systems. It then covers the implementation of these principles in nuclear reactor power systems, focusing on the role of compact heat exchangers in the combined cycle loop and applying them to the challenges facing actual nuclear power systems. The various types of compact heat exchanger surfaces and designs are given thorough consideration before the author turns his attention to discussing current and projected reactor systems, and how the novel design of these compact heat e xchangers can be applied to innovative designs, operation and safety analyses to optimize thermal efficiency. The book is written at an undergraduate level, but will be useful to practicing engineers and scientists as well.
Book Synopsis State-of-the-art Report on the Progress of Nuclear Fuel Cycle Chemistry by :
Download or read book State-of-the-art Report on the Progress of Nuclear Fuel Cycle Chemistry written by and published by . This book was released on 2018 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt: The implementation of advanced nuclear systems requires that new technologies associated with the back end of the fuel cycle are developed. The separation of minor actinides from other fuel components is one of the advanced concepts being studied to help close the nuclear fuel cycle and to improve the long-term effects on the performance of geological repositories. Separating spent fuel elements and subsequently converting them through transmutation into short-lived nuclides should considerably reduce the longterm risks associated with nuclear power generation.
Author :NEA Nuclear Science Committee. Task Force on Scientific Issues Related to Fuel Behaviour Publisher :OECD ISBN 13 : Total Pages :96 pages Book Rating :4.3/5 (91 download)
Book Synopsis Scientific Issues in Fuel Behaviour by : NEA Nuclear Science Committee. Task Force on Scientific Issues Related to Fuel Behaviour
Download or read book Scientific Issues in Fuel Behaviour written by NEA Nuclear Science Committee. Task Force on Scientific Issues Related to Fuel Behaviour and published by OECD. This book was released on 1995 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt: Dated January 1995
