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Plasma Separation Process: Betacell (BCELL) code: User's manual. [Bipolar barrier junction]

Description: The emergence of clearly defined applications for (small or large) amounts of long-life and reliable power sources has given the design and production of betavoltaic systems a new life. Moreover, because of the availability of the plasma separation program, (PSP) at TRW, it is now possible to separate the most desirable radioisotopes for betacell power generating devices. A computer code, named BCELL, has been developed to model the betavoltaic concept by utilizing the available up-to-date sour… more
Date: November 13, 1987
Creator: Taherzadeh, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculated concentrations of any radionuclide deposited on the ground by release from underground nuclear detonations, tests of nuclear rockets, and tests of nuclear ramjet engines

Description: This report presents calculated gamma radiation exposure rates and ground deposition of related radionuclides resulting from three types of event that deposited detectable radioactivity outside the Nevada Test Site complex, namely, underground nuclear detonations, tests of nuclear rocket engines and tests of nuclear ramjet engines.
Date: November 1, 1981
Creator: Hicks, H.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technological implications of SNAP reactor power system development on future space nuclear power systems

Description: Nuclear reactor systems are one method of satisfying space mission power needs. The development of such systems must proceed on a path consistent with mission needs and schedules. This path, or technology roadmap, starts from the power system technology data base available today. Much of this data base was established during the 1960s and early 1970s, when government and industry developed space nuclear reactor systems for steady-state power and propulsion. One of the largest development progra… more
Date: November 16, 1982
Creator: Anderson, R.V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Behavior of mixed-oxide fuel subjected to multiple thermal transients

Description: The microstructural behavior of irradiated mixed-oxide fuel subjected to multiple, mild thermal transients was investigated using direct electrical heating. The results demonstrate that significant intergranular porosity, accompanied by large-scale (>90%) release of the retained fission gas, developed as a result of the cyclic heating. Microstructural examination of the fuel indicated that thermal-shock-induced cracking of the fuel contributed significantly to the increased swelling and gas rel… more
Date: November 1, 1983
Creator: Fenske, G.R.; Hofman, G.L.; Neimark, L.A. & Poeppel, R.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Space nuclear safety program. Progress report, July 1983

Description: This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed here are ongoing. Results and conclusions described may change as the work continues.
Date: November 1, 1983
Creator: Bronisz, S. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Atoms to electricity. [Booklet]

Description: This booklet explains the basic technology of nuclear fission power reactors, the nuclear fuel cycle and the role of nuclear energy as one of the domestic energy resources being developed to help meet our national energy demand. Nuclear power accounted for over 16 percent of the US electric energy supply in 1986 and was second only to coal as a source of our electric power. In the 1990s, nuclear energy is expected to provide almost 20 percent of the Nation's electricity. 38 figs., 5 tabs.
Date: November 1, 1987
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Space Nuclear Safety Program. Progress report, July 1984

Description: This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed here are ongoing; results and conclusions described may change as the work continues. 10 figs.
Date: November 1, 1985
Creator: George, T.G. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Program of thermoelectric generator testing and RTG degradation mechanisms evaluation. Progress report No. 38

Description: The n-type gadolinium selenide legs after 17,500 hours continue to show reasonable agreement with the 3M Co. published thermal conductivity data. Weight loss for both coated and uncoated Si-Ge material produced by G.E. are reported. No significant discrepancies with the results previously obtained on R.C.A. material from the MHW program have been found. Thermal conductivity measurements are also in agreement. The remaining MHW generator on test, Q1-A, has accumulated 26,800 hours and performanc… more
Date: November 1, 1980
Creator: Lockwood, A. & Shields, V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pu-238 production at the Savannah River Plant

Description: Pu-238 production capability at SRP is dependent on the availability of Np-237 feed material. With continuing operation of three production reactors at SRP, production of 46 kg Pu-238 per year can be sustained. Capacity of auxiliary facilities is adequate to support the production rates.
Date: November 1, 1987
Creator: Roggenkamp, P.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Effect of irradiation on the tensile properties of niobium-base alloys

Description: The alloys Nb-1Zr and PWC-11 (Nb-1Zr-0.1C) were selected as prime candidate alloys for the SP-100 reactor. Since the mechanical properties of niobium alloys irradiated to end-of-life exposure levels of about 2 x 10SW neutrons/mS (E > 0.1 MeV) at temperatures above 1300 K were not available, an irradiation experiment (B-350) in EBR-II was conducted. Irradiation creep, impact properties, bending fatigue, and tensile properties were investigated; however, only tensile properties will be reported i… more
Date: November 1, 1986
Creator: Grossbeck, M.L.; Heestand, R.L. & Atkin, S.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Long-term exposure of pressed plutonium oxide heat sources to aquatic environments

Description: Plutonium-238 oxide fuel pellets were exposed to water for 2.5 to 6.4 yr, and the concentration of plutonium in the water was monitored. Water composition and temperature were found to be important factors in determining the rate of plutonium release into the water. Typical release rates ranged from 10 to 40 ng/m/sup 2//s in cold fresh water and from 0.3 to 11 ng/m/sup 2//s in cold sea water. Release rates in sea water varied over time and sometimes were erratic. The plutonium release per unit … more
Date: November 1, 1984
Creator: Heaton, R. C.; Patterson, J. H.; Kosiewicz, S. T.; Matlack, G. M.; Steinkruger, F. J.; Nelson, G. B. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary upper axial shield design for space reactor ground test

Description: A prototype of the SP-100 space reactor will be tested in a vacuum environment on the ground to verify the design prior to flight applications. Neutronic calculations are under way to design shielding that will provide the appropriate operational protection for both personnel and instrumentation, and will not compromise any important flight-type conditions of the reactor and shield system. This document describes the preliminary design of the shielding system. 1 ref., 11 figs.
Date: November 1, 1987
Creator: Carter, L. L. & Bunch, W. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Space Nuclear Safety Program. Progress report, June 1984

Description: This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed are ongoing; the results and conclusions described may change as the work continues. 36 figs.
Date: November 1, 1985
Creator: George, T.G. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Space Nuclear Safety Program. Progress report, August 1984

Description: This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed are ongoing; the results and conclusions described may change as the work progresses. 41 figs.
Date: November 1, 1985
Creator: George, T.G. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Environmental and radiological safety studies. Interaction of /sup 238/PuO/sub 2/ heat sources with terrestrial and aquatic environments. Progress report, July 1-September 25, 1981

Description: Although existing radioisotope thermoelectric generator designs have proved more than adequately safe, more information is continually sought about the heat sources to improve their safety. The work here includes studies of the effects on the heat sources of terrestrial and aquatic environments and also of the effects of the heat sources on various simulated environments. This progress report presents recent data from environmental chamber and aquatic experiments and gives the present status of… more
Date: November 1, 1981
Creator: Matlack, G. M. & Patterson, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SP-100 thermionic technology program annual integrated technical progress report for the period ending September 30, 1984

Description: The thermionic technology program addresses the feasibility issues of a seven-year-life thermionic fuel element (TFE) for the SP-100 Thermionic Reactor Space Power System. These issues relate to the extension of TFE lifetime from three to seven years, one of the SP-100 requirements. The technology to support three-year lifetimes was demonstrated in the earlier TFE development program conducted in the late-1960s and 1970s. Primary life-limiting factors were recognized to be thermionic emitter di… more
Date: November 1, 1984
Creator: Holland, J.W. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermionic Technology Program: A, Insulator test and evaluation: Final report

Description: The Thermionic Technology Program (TTP) consisted of two major efforts, evaluation of insulators and evaluation of thermionic converters. This report details the work performed on the insulator phase of the program. Efforts were made to better understand the mechanisms involved in the electrochemistry of insulators at elevated temperatures by modelling the ionic transport through the various layers of the insulator package. Although rigorous analytic solutions could not be obtained owing to a l… more
Date: November 30, 1987
Creator: Dobson, J.C. & Witt, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary investigations of thermionic converters utilizing HOTEMA and DFVLR electrodes

Description: Experiment results obtained from three thermionic converters using improved electrodes are reported. Two converters with ZrO/sub 2/-Mo cermet electrodes produced by a low pressure plasma spray technique at the DFVLR in Stuttgart were fabricated and tested. The first of this pair of diodes was outgassed and operated at high temperatures and did not show improved thermionic performance. The second of the two was outgassed and operated at more moderate temperatures. An encouraging barrier index of… more
Date: November 1, 1982
Creator: Saunders, M.; Danielson, L. & Huffman, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Light-Weight Radioisotope Heater Unit Final Safety Analysis Report (LWRHU FSAR): Volume 3, Nuclear Risk Analysis Document

Description: The Light-Weight Radioisotope Heater Unit (LWRHU) Final Safety Analysis Report (FSAR), Volume 2, Accident Model Document (AMD) describes potential accident scenarios during the Galileo mission and evaluates the response of the LWRHUs to the associated accident environments. Any resulting source terms, consisting of PuO2 (with Pu-238 the dominant radionuclide), are then described in terms of curies released, particle size distribution, release location, and probabilities. This volume (LWRHU-FSAR… more
Date: November 30, 1988
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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/sup 238/Pu fuel form processes. Bimonthly report, November-December 1979

Description: Progress in the Savannah River Laboratory's /sup 238/Pu Fuel Form Program is summarized. Full-scale fabrication tests continued in the Plutonium Experimental Facility (PEF) with the successful fabrication of seven additional GPHS pellets. Three pellets (GPHS Pellets 14, 15, and 16) were fabricated at off-centerline conditions to help define process limits for production of GPHS fuel pellets in the Plutonium Fuel Fabrication (PuFF) Facility. Two additional limit-test pellets (GPHS Pellets 12 and… more
Date: November 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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General purpose heat source (GPHS) clad vent set (CVS) formability study

Description: Primarily, Mound was to evaluate both improved-iridium and standard-flight iridium blanks with respect to current GPHS-CVS manufacturing processes and provide example-weld-quality CVS to the Savannah River Plant (SRP) for its weldability study. Additionally, Mound's practice of performing a final outgassing (1500/sup 0/C for 1 hr) of CVS was evaluated with respect to metallurgical properties of iridium cups and electron-beam (EB) welding characteristics of CVS subassembly components.
Date: November 3, 1986
Creator: Forrest, M. A.; McDougal, J. R. & Saylor, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cermet fuels for space power systems

Description: A refractory-metal matrix, UN-fueled cermet is a very promising fuel candidate for a wide range of multi-megawatt space reactor systems, e.g., steady-state, flexible duty-cycle, or bimodal, single- or two-phase liquid-metal cooled reactors, or thermionic reactors (Coomes et al. 1986, Takkuhen 1969, Unpublished ANL). Cermet fuel is especially promising for reactor designs that require operational strategies which incorporate rapid power changes because of its anticipated capability to withstand … more
Date: November 1, 1985
Creator: Barner, J. O.; Coomes, E. P.; Williford, R. E. & Neimark, L. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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