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Neutronic Design And Optimization Of A Porous Fuel High Temperature Gas Cooled Reactor For Space Power And Propulsion Applications
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Book Synopsis Neutronic Design and Optimization of a Porous-fuel, High-temperature, Gas-cooled Reactor for Space Power and Propulsion Applications by : Eddy Perez Cardentey
Download or read book Neutronic Design and Optimization of a Porous-fuel, High-temperature, Gas-cooled Reactor for Space Power and Propulsion Applications written by Eddy Perez Cardentey and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: ABSTRACT: Nuclear reactors are currently being considered for space power and propulsion applications. The system we examined uses a porous fuel matrix as the thermal interchange medium. Its intended use is in thermal propulsion systems, but it can also be applied to electric propulsion systems, and as a source of auxiliary power. The reactor would be used as a power source for interplanetary robotic or manned missions. Our goal was to develop an optimized relation between fuel density and reactor dimensions.
Book Synopsis Neutronic Design for a Lithium-cooled Reactor for Space Applications by : Charles L. Whitmarsh (Jr.)
Download or read book Neutronic Design for a Lithium-cooled Reactor for Space Applications written by Charles L. Whitmarsh (Jr.) and published by . This book was released on 1971 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 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 A 1-megawatt Reactor Design for Brayton-cycle Space Power Application by : C. L. Whitmarsh
Download or read book A 1-megawatt Reactor Design for Brayton-cycle Space Power Application written by C. L. Whitmarsh and published by . This book was released on 1969 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Parametric Study of the Gas-cooled Reactor Concept by : Hanford Atomic Products Operation
Download or read book A Parametric Study of the Gas-cooled Reactor Concept written by Hanford Atomic Products Operation and published by . This book was released on 1958 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis An Evaluation of High-temperature Gas-cooled Reactors by : Oak Ridge National Laboratory
Download or read book An Evaluation of High-temperature Gas-cooled Reactors written by Oak Ridge National Laboratory and published by . This book was released on 1969 with total page 236 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutronic Analysis of Horizontal-compact High Temperature Gas-cooled Reactor by : Kristina (Nuclear engineering researcher)
Download or read book Neutronic Analysis of Horizontal-compact High Temperature Gas-cooled Reactor written by Kristina (Nuclear engineering researcher) and published by . This book was released on 2023 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: To address the significant cost challenges associated with advanced reactors, a 150MWt horizontal compact high temperature gas-cooled reactor (HC-HTGR) has been proposed. The HC-HTGR has potential to reduce the capital cost of a traditional vertical oriented HTGR by 20% through reduction in reactor building volume. This benefit comes with a trade-off in control system design that requires the usage of control drums due to sagging thin rods in a horizontal layout. Commonly utilized in microreactors, a thorough investigation of control drums must be conducted in reactors with power >100MWt. Parametric studies using OpenMC were carried out to ensure its feasibility. With a uniform enriched core, 12 rotating control drums with an outer radius of 23.4407cm, 0.5cm thickness of 90% enriched B[subscript 4]C, and 0.3cm incoloy cross supports, achieved the highest shutdown margin (SDM) of 3.23%. A sensitivity study on fuel enrichment yielded a SDM of 6.29%, that satisfied the HTGRs design requirement. 2D radial and axial power peaking factor (PPF) with the new enrichment pattern was found at 1.847 and 1.344, respectively. Homogenization using ring reactivity equivalent physical transformation (RRPT) method was developed to reduce the complexity of the core and showed a good performance with a 4pcm difference in steady-state calculation. Depletion analysis was modeled to ensure the reliability of the new fuel enrichment pattern. The first cycle core sustained criticality for 2.37 years with an average enrichment of 15.5% which meets the design target goal of 2 years cycle length. Overall, the neutronics assessment of HC-HTGR core met the initial safety and design requirements.
Book Synopsis Gas Cooled Reactor Design and Safety by : International Atomic Energy Agency
Download or read book Gas Cooled Reactor Design and Safety written by International Atomic Energy Agency and published by . This book was released on 1990 with total page 252 pages. Available in PDF, EPUB and Kindle. Book excerpt: The present publication is an update of IAEA Technical Reports Series No. 235, Status of and Prospects for Gas-Cooled Reactors, published in 1984. It is a compilation of information based on submissions from Member States and is considered current as of the beginning of 1989. It describes the status of gas cooled reactors with specific emphasis on the design and safety characteristics of the various concepts that are either incorporated in operating reactors or in reactors being designed and considered for future construction and operation.
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1986 with total page 1040 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1973 with total page 516 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutronic Design for a Lithium-cooled Reactor for Space Applications by : Charles L. Whitmarsh (Jr.)
Download or read book Neutronic Design for a Lithium-cooled Reactor for Space Applications written by Charles L. Whitmarsh (Jr.) and published by . This book was released on 1971 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Development of Liquid-Vapor Core Reactors with MHD Generator for Space Power and Propulsion Applications by :
Download or read book Development of Liquid-Vapor Core Reactors with MHD Generator for Space Power and Propulsion Applications written by and published by . This book was released on 2002 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Any reactor that utilizes fuel consisting of a fissile material in a gaseous state may be referred to as a gaseous core reactor (GCR). Studies on GCRs have primarily been limited to the conceptual phase, mostly due to budget cuts and program cancellations in the early 1970's. A few scientific experiments have been conducted on candidate concepts, primarily of static pressure fissile gas filling a cylindrical or spherical cavity surrounded by a moderating shell, such as beryllium, heavy water, or graphite. The main interest in this area of nuclear power generation is for space applications. The interest in space applications has developed due to the promise of significant enhancement in fuel utilization, safety, plant efficiency, special high-performance features, load-following capabilities, power conversion optimization, and other key aspects of nuclear power generation. The design of a successful GCR adapted for use in space is complicated. The fissile material studied in the pa st has been in a fluorine compound, either a tetrafluoride or a hexafluoride. Both of these molecules have an impact on the structural material used in the making of a GCR. Uranium hexafluoride as a fuel allows for a lower operating temperature, but at temperatures greater than 900K becomes essentially impossible to contain. This difficulty with the use of UF6 has caused engineers and scientists to use uranium tetrafluoride, which is a more stable molecule but has the disadvantage of requiring significantly higher operating temperatures. Gas core reactors have traditionally been studied in a steady state configuration. In this manner a fissile gas and working fluid are introduced into the core, called a cavity, that is surrounded by a reflector constructed of materials such as Be or BeO. These reactors have often been described as cavity reactors because the density of the fissile gas is low and criticality is achieved only by means of the reflector to reduce neutron leakage from the core. Still there are problems of containment since many of the proposed vessel materials such as W or Mo have high neutron cross sections making the design of a critical system difficult. There is also the possibility for a GCR to remain in a subcritical state, and by the use of a shockwave mechanism, increase the pressure and temperature inside the core to achieve criticality. This type of GCR is referred to as a shockwave-driven pulsed gas core reactor. These two basic designs were evaluated as advance concepts for space power and propulsion.
Book Synopsis Advanced and High-temperature Gas-cooled Reactors by :
Download or read book Advanced and High-temperature Gas-cooled Reactors written by and published by . This book was released on 1969 with total page 962 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Development of a Robust Tri-carbide Fueled Reactor for Multi-megawatt Space Power and Propulsion Applications by : Samim Anghaie
Download or read book Development of a Robust Tri-carbide Fueled Reactor for Multi-megawatt Space Power and Propulsion Applications written by Samim Anghaie and published by . This book was released on 2004 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt: An innovative reactor core design based on advanced, mixed carbide fuels was analyzed for nuclear space power applications. Solid solution, mixed carbide fuels such as (U, Zr, Nb)c and (U, Zr, Ta)C offer great promise as an advanced high temperature fuel for space power reactors. This study addressed the difficulties of fabricating these solid solution fuels in traditional space reactor forms and developed methods of processing these high temperature fuels to support the fabrication of the innovative square lattice honeycomb (SLHC) fuel design. The design, in addition to better lending itself to net-shape fabrication with these advanced fuels, also permits the development of an entire class of propulsion systems from 25 to 250 kN thrust with hydrogen exit temperatures of 2800 to 3000 K for an Isp of 930 to almost 1000 seconds.
Book Synopsis Closed Brayton Cycle Power System with a High Temperature Pellet Bed Reactor Heat Source for NEP Applications by : Albert J. Juhasz
Download or read book Closed Brayton Cycle Power System with a High Temperature Pellet Bed Reactor Heat Source for NEP Applications written by Albert J. Juhasz and published by . This book was released on 1992 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Gas Cooled Ceramic Power Breeder Reactor by : J. F. Smith (Jr.)
Download or read book Gas Cooled Ceramic Power Breeder Reactor written by J. F. Smith (Jr.) and published by . This book was released on 1954 with total page 226 pages. Available in PDF, EPUB and Kindle. Book excerpt:
