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Impact Of Fuel Density On Performance And Economy Of Research Reactors
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Book Synopsis Impact of Fuel Density on Performance and Economy of Research Reactors by : IAEA
Download or read book Impact of Fuel Density on Performance and Economy of Research Reactors written by IAEA and published by International Atomic Energy Agency. This book was released on 2021-04-22 with total page 118 pages. Available in PDF, EPUB and Kindle. Book excerpt: Research reactor fuel technology continues to evolve, driven in part by international efforts to develop high density fuels to enable the conversion of more reactors from highly enriched uranium (HEU) to low enriched uranium (LEU) fuels. These high density fuels may offer economic benefits for research reactors, despite being more expensive initially, because they offer the prospect of higher per-assembly burnup, thus reducing the number of assemblies that must be procured, and more flexibility in terms of spent fuel management compared to the currently qualified and commercially available LEU silicide fuels. Additionally, these new fuels may offer better performance characteristics. This publication provides a preliminary evaluation of the impacts on research reactor performance and fuel costs from using high density fuel. Several case studies are presented and compared to illustrate these impacts.
Book Synopsis Impact of Fuel Density on Performance and Economy of Research Reactors by : International Atomic Energy Agency
Download or read book Impact of Fuel Density on Performance and Economy of Research Reactors written by International Atomic Energy Agency and published by . This book was released on 2021 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt: Research reactor fuel technology continues to evolve, driven in part by international efforts to develop high density fuels to enable the conversion of more reactors from highly enriched uranium (HEU) to low enriched uranium (LEU) fuels. These high density fuels may offer economic benefits for research reactors, despite being more expensive initially, because they offer the prospect of higher per-assembly burnup, thus reducing the number of assemblies that must be procured, and more flexibility in terms of spent fuel management compared to the currently qualified and commercially available LEU silicide fuels. Additionally, these new fuels may offer better performance characteristics. This publication provides a preliminary evaluation of the impacts on research reactor performance and fuel costs from using high density fuel. Several case studies are presented and compared to illustrate these impacts.
Book Synopsis Impact Assessment for the MIT Research Reactor Low Enrichment Uranium Fuel Fabrication Tolerances by : Dakota J. Allen
Download or read book Impact Assessment for the MIT Research Reactor Low Enrichment Uranium Fuel Fabrication Tolerances written by Dakota J. Allen and published by . This book was released on 2020 with total page 109 pages. Available in PDF, EPUB and Kindle. Book excerpt: In the framework of non-proliferation policy, the Massachusetts Institute of Technology Reactor (MITR) is planning to convert from highly enriched uranium (HEU) to low enriched uranium (LEU) fuel. A new type of high-density LEU fuel based on a monolithic U-10Mo alloy is being qualified to allow the conversion of all remaining U.S. high performance research reactors including the MITR. The purpose of this study is to understand the impact of proposed MITR LEU "FYT" fuel element fabrication tolerances on the operation and safety limits of the MITR. Therefore, the effects of fabrication specification parameters on all levels of the core, ranging from full-core alterations to individual spots on the fuel plates were analyzed. Evaluations at the design tolerances, and beyond, were conducted through neutronics and thermal hydraulics calculations. The first step was analyzing the separate effects that parameters, including enrichment, fuel mass loading, fuel plate thickness, and impurities, have on the reactor physics of the core. These analyses were used to develop curve fits to predict the effect of these parameters on the excess reactivity of fresh fuel inserted into the LEU core. These models could then be used to estimate the effect on fuel cycle length to ensure the tolerances would not cause significant changes to the operating cycle of MITR. These analyses estimated the margin to criticality present in the core and ensured that the reactivity shutdown margin (SDM) was not violated. Other parameters such as coolant channel gap and local fuel homogeneity cause primarily local impacts including the power distribution within the fuel element, and related impacts to thermal hydraulic margins. This modeling was necessary to ensure that these parameters would not cause the margin to MITR's thermal hydraulic safety limit, the onset of nucleate boiling (ONB), to be violated. The final step was a covariance analysis of the combined effects at a full-core and element level. This combined effect analysis assured that the core would maintain proper safety and operational margins with a realistic distribution of off-nominal parameters. Given the comprehensive analysis performed, the current design fabrication tolerances were determined to provide acceptable fuel cycle length and safety margins consistent with the MITR LEU preliminary safety analysis report, and a basis for updating these tolerances during planned manufacturing-scale plate fabrication demonstrations has been established.
Book Synopsis Fuel Density, Uranium Enrichment, and Performance Studies for the Advanced Neutron Source Reactor by :
Download or read book Fuel Density, Uranium Enrichment, and Performance Studies for the Advanced Neutron Source Reactor written by and published by . This book was released on 1994 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt: Consistent with the words of the budget request for the Advanced Neutron Source (ANS), DOE commissioned a study of the impact on performance of using medium- or low-enriched uranium (MEU or LEU) in the fuel of the reactor that generates the neutrons. In the course of the study, performance calculations for 19 different combinations of reactor core volume, fuel density and enrichment, power level, and other relevant parameters were carried out. Since then, another 14 cases have been analyzed at Oak Ridge to explore some of the more interesting and important configurations and to gain further insights into the tradeoffs between performance and enrichment. Furthermore, with the aid of the data from these additional cases, we have been able to correlate the most important performance parameters (peak thermal neutron flux in the reflector and core life) with reactor power, fuel density, and fuel enrichment. This enables us to investigate intermediate cases, or alternative cases that might be proposed by people within or outside the project, without the time and expense of doing completely new neutronics calculations for each new example. The main drivers of construction and operating costs are the reactor power level and the number of fuel plates to be fabricated each year; these quantities can be calculated from the correlations. The results show that the baseline two-element core design cannot be adapted to any practical fuel of greatly reduced enrichment without great performance penalties, but that a modification of the design, in which one additional fuel element is incorporated to provide extra volume for lower enrichment fuels, has the capability of using existing, or more advanced, fuel types to lower the uranium enrichment.
Author :International Atomic Energy Agency Publisher :International Atomic Energy Agency ISBN 13 :9789201450104 Total Pages :108 pages Book Rating :4.4/5 (51 download)
Book Synopsis Applications of Research Reactors by : International Atomic Energy Agency
Download or read book Applications of Research Reactors written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2014 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is a comprehensive study that reviews the current situation in a great number of applications of research reactors. It revises the contents of IAEA TECDOC-1234, The Applications of Research Reactors, giving detailed updates on each field of research reactor uses worldwide. Reactors of all sizes and capabilities can benefit from the sharing of current practices and research enabled via this updated version, which describes the requirements for practicing methods as diverse as neutron activation analysis, education and training, neutron scattering and neutron imaging, silicon doping and radioisotope production, material/fuel irradiation and testing, and some others. Many underutilised research reactors can learn how to diversify their technical capabilities, staff and potential commercial partners and users seeking research reactor services and products. The content of the publication has also been strengthened in terms of current issues facing the vast majority of research reactors by including sections describing user and customer relations as well as strategic planning considerations.
Book Synopsis Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors by : International Atomic Energy Agency
Download or read book Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors written by International Atomic Energy Agency and published by . This book was released on 2020-10-12 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
Book Synopsis Studies of the Impact of Fuel Enrichment on the Performance of the Advanced Neutron Source Reactor by :
Download or read book Studies of the Impact of Fuel Enrichment on the Performance of the Advanced Neutron Source Reactor written by and published by . This book was released on 1995 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: As part of a larger study involving several organizations, the Advanced Neutron Source (ANS) Project made performance calculations for 19 different combinations of reactor core volume, fuel density and enrichment, power level, and other relevant parameters. These calculations were performed by Idaho National Engineering Laboratory (INEL) and Oak Ridge National Laboratory (ORNL). Subsequently, ORNL analyzed 14 other cases. With the aid of data from these 33 cases, the laboratory has been able to correlate the most important performance characteristics (peak thermal flux in the reflector and core life) with fuel enrichment, fuel density, and power. The correlations permits the investigation of additional cases without going to the expense of doing completely new neutronics calculations for each new one and can be used to prepare curves showing the effects of different enrichments and of different fuel densities within the entire range from existing technology to the very advanced, as yet undeveloped fuels that have been proposed from time to time.
Book Synopsis Research Reactor Spent Fuel Management: Options and Support to Decision Making by : IAEA
Download or read book Research Reactor Spent Fuel Management: Options and Support to Decision Making written by IAEA and published by International Atomic Energy Agency. This book was released on 2021-12-14 with total page 147 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication, resulting from an IAEA coordinated research project (CRP), provides information about available strategies for research reactor spent fuel management, and presents a decision methodology to assist those selecting among several options, to identify the preferred approach for their specific situation. The decision support tools were developed to consider not only the cost of the possible research reactor spent fuel management strategies, but also the non-economic factors that might influence their selection. Examples of the technologies that are currently used by some IAEA Member States are provided. Additionally, this publication provides information about the Excel based decision-support tools developed as part of this CRP, along with case studies and tutorials to assist users.
Book Synopsis Neutronic Performance of High-density LEU Fuels in Water-moderated and Water-reflected Research Reactors by :
Download or read book Neutronic Performance of High-density LEU Fuels in Water-moderated and Water-reflected Research Reactors written by and published by . This book was released on 1996 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: At the Reduced Enrichment for Research and Test Reactors (RERTR) meeting in September 1994, Durand reported that the maximum uranium loading attainable with U3Si2 fuel is about 6.0 g U/cm3. The French Commissariat a l'Energie Atomique (CEA) plan to perform irradiation tests with 5 plates at this loading. Compagnie pour L'Etude et La Realisation de Combustibles Atomiques (CERCA) has also fabricated a few uranium nitride (UN) plates with a uranium density in the fuel meat of 7.0 g/cm3 and found that UN is compatible with the aluminum matrix at temperatures below 500 C. High density dispersion fuels proposed for development include U-Zr(4 wt%)-Nb(2 wt%), U-Mo(5 wt%), and U-Mo(9 wt%). The purpose of this note is to examine the relative neutronic behavior of these high density fuels in a typical light water-reflected and water-moderated MTR-type research reactor. The results show that a dispersion of the U-Zr-Nb alloy has the most favorable neutronic properties and offers the potential for uranium densities greater than 8.0 g/cm3. On the other hand, UN is the least reactive fuel because of the relatively large 14N(n, p) cross section. For a fixed value of k{sub eff}, the required 235U loading per fuel element is least for the U-Zr-Nb fuel and steadily increases for the U-Mo(5%), U-Mo(9%), and UN fuels. Because of volume fraction limitations, the UO2 dispersions are only useful for uranium densities below 5.0 g/cm3. In this density range, however, UO2 is more reactive than U3Si2.
Book Synopsis Effects of Uranium Dioxide Fuel Microstructure and Density on Fuel In-reactor Performance by : Lena Hansson
Download or read book Effects of Uranium Dioxide Fuel Microstructure and Density on Fuel In-reactor Performance written by Lena Hansson and published by . This book was released on 1988 with total page 53 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Assessment of Nuclear Fuels Using Radiographic Thickness Measurement Method by :
Download or read book Assessment of Nuclear Fuels Using Radiographic Thickness Measurement Method written by and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Convert branch of the National Nuclear Security Administration (NNSA) Global Threat Reduction Initiative (GTRI) focuses on the development of high uranium density fuels for research and test reactors for nonproliferation. This fuel is aimed to convert low density high enriched uranium (HEU) based fuel to high density low enriched uranium (LEU) based fuel for high performance research reactors (HPRR). There are five U.S. reactors that fall under the HPRR category, including: the Massachusetts Institute of Technology Reactor (MITR), the National Bureau of Standards Reactor (NBSR), the Missouri University Research Reactor (UMRR), the Advanced Test Reactor (ATR), and the High Flux Isotope Reactor (HFIR). U-Mo alloy fuel phase in the form of either monolithic or dispersion foil type fuels, such as ATR Full-size In center flux trap Position (AFIP) and Reduced Enrichment for Research and Test Reactor (RERTR), are being designed for this purpose. The fabrication process1 of RERTR is susceptible to introducing a variety of fuel defects. A dependable quality control method is required during fabrication of RERTR miniplates to maintain the allowable design tolerances, therefore evaluating and analytically verifying the fabricated miniplates for maintaining quality standards as well as safety. The purpose of this work is to analyze the thickness of the fabricated RERTR-12 miniplates using non-destructive technique to meet the fuel plate specification for RERTR fuel to be used in the ATR.
Book Synopsis Uranium Enrichment and Nuclear Weapon Proliferation by : Allan S. Krass
Download or read book Uranium Enrichment and Nuclear Weapon Proliferation written by Allan S. Krass and published by Routledge. This book was released on 2020-11-20 with total page 325 pages. Available in PDF, EPUB and Kindle. Book excerpt: Originally published in 1983, this book presents both the technical and political information necessary to evaluate the emerging threat to world security posed by recent advances in uranium enrichment technology. Uranium enrichment has played a relatively quiet but important role in the history of efforts by a number of nations to acquire nuclear weapons and by a number of others to prevent the proliferation of nuclear weapons. For many years the uranium enrichment industry was dominated by a single method, gaseous diffusion, which was technically complex, extremely capital-intensive, and highly inefficient in its use of energy. As long as this remained true, only the richest and most technically advanced nations could afford to pursue the enrichment route to weapon acquisition. But during the 1970s this situation changed dramatically. Several new and far more accessible enrichment techniques were developed, stimulated largely by the anticipation of a rapidly growing demand for enrichment services by the world-wide nuclear power industry. This proliferation of new techniques, coupled with the subsequent contraction of the commercial market for enriched uranium, has created a situation in which uranium enrichment technology might well become the most important contributor to further nuclear weapon proliferation. Some of the issues addressed in this book are: A technical analysis of the most important enrichment techniques in a form that is relevant to analysis of proliferation risks; A detailed projection of the world demand for uranium enrichment services; A summary and critique of present institutional non-proliferation arrangements in the world enrichment industry, and An identification of the states most likely to pursue the enrichment route to acquisition of nuclear weapons.
Book Synopsis Nuclear Energy Basic Principles by : International Atomic Energy Agency
Download or read book Nuclear Energy Basic Principles written by International Atomic Energy Agency and published by . This book was released on 2008 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Describes the rationale and vision for the peaceful use of nuclear energy. The publication identifies the basic principles that nuclear energy systems must satisfy to fulfil their promise of meeting growing global energy demands.
Book Synopsis Relative Neutronic Performance of Proposed High-density Dispersion Fuels in Water-moderated and D2O-reflected Research Reactors by :
Download or read book Relative Neutronic Performance of Proposed High-density Dispersion Fuels in Water-moderated and D2O-reflected Research Reactors written by and published by . This book was released on 1996 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper provides an overview of the neutronic performance of an idealized research reactor using several high density LEU fuels that are being developed by the RERTR program. High-density LEU dispersion fuels are needed for new and existing high-performance research reactors and to extend the lifetime of fuel elements in other research reactors. This paper discusses the anticipated neutronic behavior of proposed advanced fuels containing dispersions of U3Si2, UN, U2Mo and several uranium alloys with Mo, or Zr and Nb. These advanced fuels are ranked based on the results of equilibrium depletion calculations for a simplified reactor model having a small H2O-cooled core and a D2O reflector. Plans have been developed to fabricate and irradiate several uranium alloy dispersion fuels in order to test their stability and compatibility with the matrix material and to establish practical loading limits.
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 Performance Analysis Review of Thorium TRISO Coated Particles During Manufacture, Irradiation and Accident Condition Heating Tests by : International Atomic Energy Agency
Download or read book Performance Analysis Review of Thorium TRISO Coated Particles During Manufacture, Irradiation and Accident Condition Heating Tests written by International Atomic Energy Agency and published by IAEA Tecdoc. This book was released on 2015 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is the outcome of an IAEA coordinated research project on near term and promising long term options for deployment of thorium based nuclear energy. It is based on the compilation and analysis of available results on thorium tristructural isotropic (TRISO) coated particle fuel performance in manufacturing during irradiation and accident condition heating tests. As a result, the project participants concluded that the performance statistics for the high enriched thoria urania TRISO fuel system are in perfect concert with those state of the art requirements for present day high temperature reactor concepts.
Book Synopsis Approaches for Assessing the Economic Competitiveness of Small and Medium Sized Reactors by : International Atomic Energy Agency
Download or read book Approaches for Assessing the Economic Competitiveness of Small and Medium Sized Reactors written by International Atomic Energy Agency and published by . This book was released on 2013 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication assists existing and potential stakeholders in the definition of competitive approaches regarding design and deployment of small and medium sized reactors (SMR). It provides a framework for assessment of the investment attractiveness of nuclear power plant projects that adopts small reactor to be deployed in multi-modules and incorporate modularization construction technology. Main chapters detail past experience and future plans in several IAEA Member States and present the suite of models to assist designers and guide potential users on the economic performance and investment attractiveness of SMRs. A framework for the consolidated application of such models is also suggested. The annexes, contributed by Member States, provide in depth descriptions of different assessment models and give examples of their application.
