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An Experimental Shield Test Facility for the Development of Minimum Weight Shields for Compact Reactor Power Systems

Description: Discussions are given of the characteristics of fission-source plate, graphite reactor, and pool-type reactor facilities applicable to development studies of minimum weight shielding materials. Advantages of a proposed SNAP dual-purpose shielding facility are described in terms of a disk-shaped fission-source plate, reactor, and building. A program for the study of advanced shielding materials is discussed for materials and configuations to be evaluted with the fission-source plate, the testing of the prototype at high-power levels, and full-power tests on the actual reactor.
Date: August 7, 1959
Creator: Tomlinson, R. L.
Partner: UNT Libraries Government Documents Department

Direct conversion technology

Description: The overall objective of the Direct Conversion Technology task is to develop an experimentally verified technology base for promising direct conversion systems that have potential application for energy conservation in the end-use sectors. This report contains progress of research on the Alkali Metal Thermal-to-Electric Converter (AMTEC) and on the Two-Phase Liquid-Metal MHD Electrical Generator (LMMHD) for the period January 1, 1991 through December 31, 1991. Research on AMTEC and on LMMHD was initiated during October 1987. Reports prepared on previous occasions (Refs. 1--5) contain descriptive and performance discussions of the following direct conversion concepts: thermoelectric, pyroelectric, thermionic, thermophotovoltaic, thermoacoustic, thermomagnetic, thermoelastic (Nitionol heat engine); and also, more complete descriptive discussions of AMTEC and LMMHD systems.
Date: January 7, 1992
Creator: Massier, P.F.; Back, L.H.; Ryan, M.A. & Fabris, G.
Partner: UNT Libraries Government Documents Department

The Tower Shielding Facility: Its glorious past

Description: The Tower Shielding Facility (TSF) is the only reactor facility in the US that was designed and built for radiation-shielding studies in which both the reactor source and shield samples could be raised into the air to allow measurements to be made without interference from ground scattering or other spurious effects. The TSF proved its usefulness as many different programs were successfully completed. It became active in work for the Defense Atomic Support Agency (DASA) Space Nuclear Auxiliary Power, Defense Nuclear Agency, Liquid Metal Fast Breeder Reactor Program, the Gas-Cooled and High-Temperature Gas-Cooled Reactor programs, and the Japanese-American Shielding Program of Experimental Research, just to mention a few of the more extensive ones. The history of the TSF as presented in this report describes the various experiments that were performed using the different reactors. The experiments are categorized as to the programs which they supported and placed in corresponding chapters. The experiments are described in modest detail, along with their purpose when appropriate. Discussion of the results is minimal, but references are given to more extensive topical reports.
Date: May 7, 1997
Creator: Muckenthaler, F.J.
Partner: UNT Libraries Government Documents Department

Kilowatt isotope power system. Component test report for the ground demonstration system pump

Description: The purpose of this test was to demonstrate that the System Pump utilized for the developmental program to be conducted on the Kilowatt Isotope Power System (KIPS) fulfilled the requirements of Test Procedure 398, Component Test Procedure for the GDS System Pump. Results of the testing performed on the System Pump are presented.
Date: November 7, 1977
Partner: UNT Libraries Government Documents Department

Some scoping experiments for a space reactor

Description: Some scoping experiments were performed to evaluate fuel performance in a lithium heat pipe reactor operating at a nominal 1500K heat pipe temperature. Fuel-coolant and fuel-coolant-clad relationships showed that once a failed heat pipe occurs temperatures can rise high enough so that large concentrations of uranium can be transported by the vapor phase. Upon condensation this uranium would be capable of penetrating heat pipes adjacent to the failed pipe. The potential for propagation of failure exists with UO/sub 2/ and a lithium heat pipe. Changing the composition of the metal of the heat pipe would have only a second order effect on the kinetics of the failure mechanism. Uranium carbide and nitride were considered as potential fuels which are nonreactive in a lithium environment. At high temperatures the nitride would be favored because of its better compatibility with potential cladding materials. Compositions of UN with small additions of YN appear to offer very attractive properties for a compact high temperature high power density reactor.
Date: July 7, 1983
Creator: Alexander, C.A. & Ogden, J.S.
Partner: UNT Libraries Government Documents Department

Materials Technology Support for Radioisotope Power Systems Final Report

Description: Over the period of this sponsored research, UDRI performed a number of materials related tasks that helped to facilitate increased understanding of the properties and applications of a number of candidate program related materials including; effects of neutron irradiation on tantalum alloys using a 500kW reactor, thermodynamic based modeling of the chemical species in weld pools, and the application of candidate coatings for increased oxidation resistance of FWPF (Fine Weave Pierced Fabric) modules.
Date: October 7, 2008
Creator: Kramer, Daniel P. & Barklay, Chadwick D.
Partner: UNT Libraries Government Documents Department

Thermo-physics technical note No. 37: SNAP- 10A, Stainless Steel-316 vessel wall ablation. Final report

Description: The altitudes and times of ablation have been determined for the SNAP-10A, SS-316 vessel wall reentering under various conditions. The results are confined to one typical location on the reactor and to one typical reentry trajectory. The location is the side wall of the vessel and the trajectory is the one used in NAA-SR-8303.
Date: December 7, 1964
Creator: Montgomery, L.D.
Partner: UNT Libraries Government Documents Department

SPR-9 concept definition study: FY 1986 summary

Description: This report summarizes the results of work undertaken to advance design of the SPR-9 MMW power reactor. Gas-cooled thermal reactors coupled with Brayton cycle power conversion appear feasible and have several attractive features for multi-megawatt space power systems. The high temperature capability of the reactor removes it as the limiting component on system performance. The low fuel inventories required make systems based on thermal reactors a lesser safeguard risk. However, an advanced radiator design must be developed to reduce system mass. (JDH)
Date: October 7, 1986
Creator: Walter, C.E.
Partner: UNT Libraries Government Documents Department

Thermo-physics technical note No. 56: a parameter study of properties and mechanisms affecting the reentry ablation of SNAP fuel particles

Description: The results are presented of a parameter survey of the properties and mechanisms affecting the reentry ablation of SNAP fuel particles. The following properties and mechanisms were studied: aerodynamic heating, oxidation, oxide vaporization, metal vaporization, particle emissivity, specific heat, density, velocity, and initial size. These studies were made for particle release altitudes ranging from 170,000 to 228,000 feet.
Date: December 7, 1965
Creator: Sayles, C.W.
Partner: UNT Libraries Government Documents Department