Download or read book Assessment of a Hot Hydrogen Nuclear Propulsion Fuel Test Facility written by and published by . This book was released on 1991 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: Subsequent to the announcement of the Space Exploration Initiative (SEI), several studies and review groups have identified nuclear thermal propulsion as a high priority technology for development. To achieve the goals of SEI to place man on Mars, a nuclear rocket will operate at near 2700K and in a hydrogen environment at near 60 atmospheres. Under these conditions, the operational lifetime of the rocket will be limited by the corrosion rate at the hydrogen/fuel interface. Consequently, the Los Alamos National Laboratory has been evaluating requirements and design issues for a test facility. The facility will be able to directly heat fuel samples by electrical resistance, microwave deposition, or radio frequency induction heating to temperatures near 3000K. Hydrogen gas at variable pressure and temperatures will flow through the samples. The thermal gradients, power density, and operating times envisioned for nuclear rockets will be duplicated as close as reasonable. The post-sample flow stream will then be scrubbed and cooled before reprocessing. The baseline design and timetable for the facility will be discussed. 7 refs.
Download or read book Hot Hydrogen Test Facility written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The core in a nuclear thermal rocket will operate at high temperatures and in hydrogen. One of the important parameters in evaluating the performance of a nuclear thermal rocket is specific impulse, ISp. This quantity is proportional to the square root of the propellant's absolute temperature and inversely proportional to square root of its molecular weight. Therefore, high temperature hydrogen is a favored propellant of nuclear thermal rocket designers. Previous work has shown that one of the life-limiting phenomena for thermal rocket nuclear cores is mass loss of fuel to flowing hydrogen at high temperatures. The hot hydrogen test facility located at the Idaho National Lab (INL) is designed to test suitability of different core materials in 2500°C hydrogen flowing at 1500 liters per minute. The facility is intended to test non-uranium containing materials and therefore is particularly suited for testing potential cladding and coating materials. In this first installment the facility is described. Automated Data acquisition, flow and temperature control, vessel compatibility with various core geometries and overall capabilities are discussed.
Download or read book Space Nuclear Thermal Propulsion Test Facilities Subpanel written by and published by . This book was released on 1993 with total page 184 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Space Nuclear Propulsion for Human Mars Exploration written by National Academies of Sciences Engineering and Medicine and published by . This book was released on 2021-11-12 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Space Nuclear Propulsion for Human Mars Exploration identifies primary technical and programmatic challenges, merits, and risks for developing and demonstrating space nuclear propulsion technologies of interest to future exploration missions. This report presents key milestones and a top-level development and demonstration roadmap for performance nuclear thermal propulsion and nuclear electric propulsion systems and identifies missions that could be enabled by successful development of each technology.
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1994 with total page 892 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book An Assessment of Testing Requirement Impacts on Nuclear Thermal Propulsion Ground Test Facility Design written by and published by . This book was released on 1993 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Programs to develop solid core nuclear thermal propulsion (NTP) systems have been under way at the Department of Defense (DoD), the National Aeronautics and Space Administration (NASA), and the Department of Energy (DOE). These programs have recognized the need for a new ground test facility to support development of NTP systems. However, the different military and civilian applications have led to different ground test facility requirements. The Department of Energy (DOE) in its role as landlord and operator of the proposed research reactor test facilities has initiated an effort to explore opportunities for a common ground test facility to meet both DoD and NASA needs. The baseline design and operating limits of the proposed DoD NTP ground test facility are described. The NASA ground test facility requirements are reviewed and their potential impact on the DoD facility baseline is discussed.
Download or read book Preliminary Design of a Hot Hydrogen Test Loop for Nuclear Thermal Propulsion Applications written by Will Searight and published by . This book was released on 2020 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Thermal Rockets (NTRs) are one of the leading propulsion system candidates in deep space exploration due to their high thrust to weight ratio and specific impulse, reducing both the cost of deep space missions and the exposure of payloads to space radiation. To aid in NTR system design being done by Ultra Safe Nuclear Corporation, this work presents a preliminary design of a hot hydrogen test loop facility that can subject NTR tie tubes to NTR hydrogen flow conditions. Tie tubes are channel elements through which hot hydrogen coolant/propellant flows in the reactor core; these hydrogen facing components will be subject to plasma embrittlement as hydrogen gas begins exhibiting bulk plasma behavior. It is critical to characterize these effects for NTR longevity in deep space missions, and this test loop design will provide initial data at 1200 °C, moving to 2700 °C in a later design. Preliminary design work was conducted using ANSYS 2020 R1 Student Edition, using both Steady-State Thermal and Fluent models to obtain temperature and velocity distributions in the loop pipes, hydrogen, and tie tubes. The Fluent model was simplified to a linear pipe flow design to improve test section flow results. The heating section was assumed to have a heat load evenly distributed over the pipe surface. In practice, heating will need to provide an equivalent power over the smaller contact area. The selection of a FeCrAl alloy as the test loop pipe material was validated for loop operating conditions, and the loop provided sufficient heating to the hydrogen and tie tube for a variety of pipe cross-sectional areas and thicknesses. The flow was found to be largely laminar for the operating mass flow rate and pressure. The loop produced suitable operating temperatures even under high vacuum conditions, although further study of the cooling system is needed to verify forced convection can be obtained.
Download or read book An Assessment of Hydrogen Generation for the PBF Severe Fuel Damage Scoping and 1 1 Test written by August W. Cronenberg and published by . This book was released on 1987 with total page 106 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1992 with total page 752 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book High Temperature Gas cooled Reactors written by Tetsuaki Takeda and published by Academic Press. This book was released on 2021-02-24 with total page 478 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-Temperature Gas Reactors is the fifth volume in the JSME Series on Thermal and Nuclear Power Generation. Series Editor Yasuo Koizumi and his Volume editors Tetsuaki Takeda and Yoshiyuki Inagaki present the latest research on High-Temperature Gas Reactor (HTGR) development and utilization, beginning with an analysis of the history of HTGRs. A detailed analysis of HTGR design features, including reactor core design, cooling tower design, pressure vessel design, I&C factors and safety design, provides readers with a solid understanding of how to develop efficient and safe HTGR within a nuclear power plant. The authors combine their knowledge to present a guide on the safety of HTGRs throughout the entire reactor system, drawing on their unique experience to pass on lessons learned and best practices to support professionals and researchers in their design and operation of these advanced reactor types. Case studies of critical testing carried out by the authors provide the reader with firsthand information on how to conduct tests safely and effectively and an understanding of which responses are required in unexpected incidents to achieve their research objectives. An analysis of technologies and systems in development and testing stages offer the reader a look to the future of HTGRs and help to direct and inform their further research in heat transfer, fluid-dynamics, fuel options and advanced reactor facility selection. This volume is of interest for nuclear and thermal energy engineers and researchers focusing on HTGRs, HTGR plant designers and operators, regulators, post graduate students of nuclear engineering, national labs, government officials and agencies in power and energy policy and regulations. Written by the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits Considers the societal impact and sustainability concerns and goals throughout the discussion Includes safety factors and considerations, as well as unique results from performance testing of HTGR systems.
Download or read book Ground Test Facility for SEI Nuclear Rocket Engines written by and published by . This book was released on 1992 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Thermal Propulsion (NTP) has been identified as a critical technology in support of the NASA Space Exploration Initiative (SEI). In order to safely develop a reliable, reusable, long-lived flight engine, facilities are required that will support ground tests to qualify the nuclear rocket engine design. Initial nuclear fuel element testing will need to be performed in a facility that supports a realistic thermal and neutronic environment in which the fuel elements will operate at a fraction of the power of a flight weight reactor/engine. Ground testing of nuclear rocket engines is not new. New restrictions mandated by the National Environmental Protection Act of 1970, however, now require major changes to be made in the manner in which reactor engines are now tested. These new restrictions now preclude the types of nuclear rocket engine tests that were performed in the past from being done today. A major attribute of a safely operating ground test facility is its ability to prevent fission products from being released in appreciable amounts to the environment. Details of the intricacies and complications involved with the design of a fuel element ground test facility are presented in this report with a strong emphasis on safety and economy.
Download or read book Ground Test Facilities for Evaluating Nuclear Thermal Propulsion Engines and Fuel Elements written by and published by . This book was released on 1992 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Interagency panels evaluating nuclear thermal propulsion development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and design issues of a proposed ground test complex for evaluating nuclear thermal propulsion engines and fuel elements being developed for the Space Nuclear Thermal Propulsion (SNTP) program. 2 refs.
Download or read book The Development of Nuclear Thermal Propulsion Technology for Use in Space written by United States. Congress. House. Committee on Science, Space, and Technology. Subcommittee on Investigations and Oversight and published by . This book was released on 1993 with total page 410 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Test Facilities for Evaluating Nuclear Thermal Propulsion Systems written by and published by . This book was released on 1992 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Interagency panels evaluating nuclear thermal propulsion (NTP) development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and baseline performance of some of the major subsystems designed to support a proposed ground test complex for evaluating nuclear thermal propulsion fuel elements and engines being developed for the Space Nuclear Thermal Propulsion (SNTP) program. Some preliminary results of evaluating this facility for use in testing other NTP concepts are also summarized.
Download or read book Liquid Rocket Valve Components written by H. J. Ellis and published by . This book was released on 1973 with total page 156 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Experiments in the large scale vented combustion test facility series s01 quiescent vented combustion tests with central ignition in hydrogen air mixtures in the full volume geometry written by R. K. Kumar and published by . This book was released on 1997 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The btf-105 experiment in the blowdown test facility is one of a series of experiments sponsored by the candu owners group (cog) to determine the release, transport and deposition of fission products from nuclear fuel under high-temperature transient conditions. the btf-105 experiment has been broken up into two tests: btf-105a and btf-105b. the btf-105a test is a precursor to the btf-105b test, which will generate fission product release data used to benchmark candu safety analysis codes. the btf-105a test will be used to assess instrumentation and procedures to be used during btf-105b, and to generate correlations between fuel sheath and fuel centreline temperatures. fission product release and transport data will also be obtained from low burnup fuel. the btf-105a test consists of a fuel stringer containing a single unirradiated instrumented zircaloy-clad uo2 fuel element. the assembly will be irradiated at a linear power of 50 kw/m for 10 days to establish an inventory of fission products in the fuel. following the soak irradiation, the stringer will be subjected to a coolant blowdown where the volume average temperature of the uo2 will rise to and be maintained at about 1600-1800 degrees c for about 10 minutes. the fuel element is predicted to fail during the ramp up to this temperature due to complete oxidation of the sheath. fission products released during the transient will be monitored by gamma spectrometers. following the test, the fuel stringer will be removed from the reactor and destructively examined in the crl hot cells. grab samples from inside the test section will also be removed and analyzed for fission products. this report presents an overall plan for the activities to be completed before, during and after the btf-105a blowdown test.
Download or read book Principles of Nuclear Rocket Propulsion written by William J. Emrich Jr. and published by Elsevier. This book was released on 2023-03-11 with total page 430 pages. Available in PDF, EPUB and Kindle. Book excerpt: Principles of Nuclear Rocket Propulsion, Second Edition continues to put the technical and theoretical aspects of nuclear rocket propulsion into a clear and unified presentation, providing an understanding of the physical principles underlying the design and operation of nuclear fission-based rocket engines. This new edition expands on existing material and adds new topics, such as antimatter propulsion, nuclear rocket startup, new fuel forms, reactor stability, and new advanced reactor concepts. This new edition is for aerospace and nuclear engineers and advanced students interested in nuclear rocket propulsion. - Provides an understanding of the physical principles underlying the design and operation of nuclear fission-based rocket engines - Includes a number of example problems to illustrate the concepts being presented - Contains an electronic version with interactive calculators and rotatable 3D figures to demonstrate the physical concepts being presented - Features an instructor website that provides detailed solutions to all chapter review questions
