Search Results

Advanced search parameters have been applied.

Artificial Heart Development Program. Phase III. Quarterly progress report, January 1, 1977--March 31, 1977

Description: Technical progress and accomplishments on the active program tasks for the reporting period are presented. At the start of this reporting period the work program was directed to the completion of the IVBM system and the design of the Mark I Prototype System. As of February 1, 1977, however, the program was redirected, by ERDA decision, to provide an orderly phase out to be concluded by September 30, 1977. The aim of the present work plan is to provide as much useful information as possible. (TFD)
Date: January 1, 1977
Partner: UNT Libraries Government Documents Department

Prandtl Number Dependent Natural Convection with Internal Heat Sources

Description: Natural convection plays an important role in determining the thermal load from debris accumulated in the reactor vessel lower head during a severe accident. Recently, attention is being paid to the feasibility of external vessel flooding as a severe accident management strategy and to the phenomena affecting the success path for retaining the molten core material inside the vessel. The heat transfer inside the molten core material can be characterized by the strong buoyancy-induced flows resulting from internal heating due to decay of fission products. The thermo-fluid dynamic characteristics of such flow depend strongly on the thermal boundary conditions. The spatial and temporal variation of heat flux on the pool wall boundaries and the pool superheat are mainly characterized by the natural convection flow inside the molten pool. In general, the natural convection heat transfer phenomena involving the internal heat generation are represented by the modified Rayleigh number (Ra’), which quantifies the internal heat source and hence the strength of the buoyancy force. In this study, tests were conducted in a rectangular section 250 mm high, 500 mm long and 160 mm wide. Twenty-four T-type thermocouples were installed in the test section to measure temperatures. Four T-type thermocouples were used to measure the boundary temperatures. The thermocouples were placed in designated locations after calibration. A direct heating method was adopted in this test to simulate the uniform heat generation. The experiments covered a range of Ra' between 1.5x106 and 7.42x1015 and the Prandtl number (Pr) between 0.7 and 6.5. Tests were conducted with water and air as simulant. The upper and lower boundary conditions were maintained uniform. The results demonstrated feasibility of the direct heating method to simulate uniform volumetric heat generation. Particular attentions were paid to the effect of Pr on natural convection heat transfer within the rectangular pool.
Date: June 1, 2004
Creator: Lee, Kang Hee; Lee, Seung Dong; Suh, Kune Y.; Rempe, Joy L.; Cheung, Fan-Bill & Kim, Sang B.
Partner: UNT Libraries Government Documents Department

Assessment of radioisotope heaters for remote terrestrial applications

Description: This paper examines the feasibility of using radioisotope byproducts for special heating applications at remote sites in Alaska and other cold regions. The investigation included assessment of candidate radioisotope materials for heater applications, identification of the most promising cold region applications, evaluation of key technical issues and implementation constraints, and development of conceptual heater designs for candidate applications. Strontium-90 (Sr-90) was selected as the most viable fuel for radioisotopic heaters used in terrestrial applications. Opportunities for the application of radioisotopic heaters were determined through site visits to representative Alaska installations. Candidate heater applications included water storage tanks, sludge digesters, sewage lagoons, water piping systems, well-head pumping stations, emergency shelters, and fuel storage tank deicers. Radioisotopic heaters for water storage tank freeze-up protection and for enhancement of biological waste treatment processes at remote sites were selected as the most promising applications.
Date: May 1, 1987
Creator: Uherka, K.L.
Partner: UNT Libraries Government Documents Department

Nuclear-Powered Artificial Heart Prototype System Development Program: Phase III. Quarterly progress report, October 1, 1976--December 31, 1976

Description: Technical progress and accomplishments on the active program tasks 49 through 62 on the development of a nuclear-powered artificial heart are reported. The tasks include waste heat rejection, systems studies, IVBM modification design, IVBM fabrication, IVBM performance testing, IVBM system life testing, field support, reliability and quality assurance, Mark I thermal insulation design, and Mark I thermal converter design. (TFD)
Date: January 1, 1976
Partner: UNT Libraries Government Documents Department

ERDA artificial heart program workshop. Final report, September 1, 1975--August 31, 1976

Description: The major conclusions of the ERDA Artificial Heart Program Workshop are that the concept of a biologically compatible mechanical device which can totally replace the heart is sound, that such a device is needed as an alternative to cardiac transplantation and that its development is a realistic goal. The major recommendation of the committee is that an ERDA program with primary orientation toward development of a total heart replacement should continue, with assured funding about 50 percent higher than at present, for a minimum of 3 additional years at which time another major review should take place. To achieve better management of the program it is recommended that the present contract effort be reorganized under one prime contractor with responsibility for development and demonstration of the ERDA artificial heart system. The formation of a joint artificial heart advisory committee to improve coordination between ERDA and NHLI is also recommended. The committee suggests future policies and directions which it believes will lead to more effective use of funds available for specific aspects of the program. These include the nuclear heart source, engine, blood pump, biomaterials and overall system reliability. Possible future goals for the program are also proposed.
Date: August 1, 1976
Creator: Kantrowitz, A.; Altieri, F. & Beall, A.
Partner: UNT Libraries Government Documents Department

Nuclear-Powered Artificial Heart Prototype System Development Program: Phase III. Quarterly progress report, January 1, 1976--March 31, 1976

Description: Research progress is reported on tasks 35 through 46 of phase III of the program. The tasks include: thermal insulation and thermal protection; thermal converter; blood pump and power coupling; thermal and hydraulic R and D; system integration and interfacing; IVBM system performance testing; IVBM system fabrication and fabrication support; added IVBM blood pump fabrication; IVBM system life testing; IVBM field support; and reliability and quality assurance. (TFD)
Date: January 1, 1976
Partner: UNT Libraries Government Documents Department

Reliability studies for the nuclear-powered artificial heart program

Description: By assuming that the failures of an artificial heart system with a mean life of 10 y can be modeled by a particular probability distribution, both the probability of a failure in the system within t years and the reliability required of each subsystem and component were investigated.
Date: April 1, 1976
Creator: Horita, M. & Zeigler, R. K.
Partner: UNT Libraries Government Documents Department

Quarterly progress report on Artificial heart development program. Phase III April 1, 1977 through June 30, 1977

Description: Technical progress and accomplishments on the active program tasks for the period from April 1, 1977 through June 30, 1977 are reported. The tasks include: (1) Blood Pump Engineering Support; (2) IVBM System Engineering Support; (3) Blood Pump Fabrication and Repair; (4) IVBM System Repair and Support; and (5) Quality Assurance. (TFD)
Date: January 1, 1977
Partner: UNT Libraries Government Documents Department

TOUGH+/GasH20 study of the effects of a heat source buried in theMartian permafrost

Description: We use TOUGH+/GasH2O to study the effects of a heat sourceburied in the Martian permafrost to evaluate the possibility ofestablishing a wet zone of liquid water, in which terrestrialmicroorganisms could survive and multiply. Analysis of the problemindicates that (1) only a limited permafrost volume (not exceeding 0.35 min radius) is affected, (2) a "wet" zone with limited amounts of liquidwater de-velops (not exceeding 8 and 0.7 kg for a 250 W and a 62.5 Wsource, respectively), (3) the wet zone per-sists for a long time,becomes practically stationary after t = 20 sols because of venting intothe Martian atmosphere, and its thickness is limited and decreases slowlyover time, (4) a "dry" zone (where SG>0.9) evolves, continues toexpand (albeit slowly) with time, but its extent remains limited, and (5)the ice front surrounding the wet zone is self-sharpening. For a range ofinitial conditions investigated, evolution of the liquid water massoccurs at approximately the same rate, reaches roughly the same maximum,and occurs at about the same time (10 to 20 sols; 1 sol = 24.39hours).
Date: May 12, 2006
Creator: Moridis, George J. & Pruess, Karsten
Partner: UNT Libraries Government Documents Department

Artificial heart development program. Volume II. System support. Phase III summary report. Period covered: July 1, 1973--September 30, 1977

Description: Appendix A covers major activities of the Artificial Heart Development program that supported the design, fabrication, and test of the system demonstration units. Section A.1.0 provides a listing beyond that of the body of the report on the components needed for an implantation. It also presents glove box sterilization calibration results and results of an extensive mock circulation calibration. Section A.2.0 provides detail procedures for assembly, preparing for use, and the use of the system and major components. Section A.3.0 covers the component research and development activities undertaken to improve components of the existing system units and to prepare for a future prototype system. Section A.4.0 provides a listing of the top assembly drawings of the major systems variations fabricated and tested.
Date: January 1, 1977
Partner: UNT Libraries Government Documents Department

Artificial heart development program. Volume I. System development. Phase III summary report

Description: The report documents efforts and results in the development of the power system portions of a calf implantable model of nuclear-powered artificial heart. The primary objective in developing the implantable model was to solve the packaging problems for total system implantation. The power systems portion is physically that portion of the implantable model between the Pu-238 heat sources and the blood pump ventricles. The work performed had two parallel themes. The first of these was the development of an integrated implantable model for bench and animal experiments plus design effort on a more advanced model. The second was research and development on components of the system done in conjunction with the development of the implantable model and to provide technology for incorporation into advanced models plus support to implantations, at the University of Utah, of the systems blood pumping elements when driven by electric motor. The efforts and results of implantable model development are covered, mainly, in the text of the report. The research and development efforts and results are reported, primarily, in the appendices (Vol. 2).
Date: January 1, 1977
Partner: UNT Libraries Government Documents Department

Data sheets for PPO radioisotopic fuel

Description: PPO is the acronym for Pure Plutoniunn Oxide. The thermal energy of this fuel results from the radioactive decay of /sup 238/ Pu this energy is converted into usable electric power for space probe or other applications. The basic fuel module associated with the current MHW heat source is a PPO sphere 1.465 plus or minus 0.015 in. in dia and containing 100 plus or minus 2 thermal watts. The spheres are individually encapsulated and then assembled into geometric arrays to form the working heat source. The following document lists certain properties of PuO/sub 2/ with emphasis on behavior at the proposed operational conditions being discussed. Since many of the desired properties are still being determined, the information is preliminary in nature and will be revised periodically. This report is the first revision of LA-5160-MS (issued 2/ 73) and incorporates additional and more specific data. (auth)
Date: December 1, 1973
Creator: Keenan, T. K.; Kent, R. A.; Mulford, R. N. R. & Shupe, M. W.
Partner: UNT Libraries Government Documents Department

Radioisotope heat source development for an artificial heart device. Phase I. Final report

Description: Detailed parametric analyses of vented radioisotope heat sources were performed to arrive at a design optimized in weight, volume, and safety. The top rated system was a single-layer Hafnalloy heat source. Due to limited mechanical property, compatibility, and heat source test data available for this material, however, the three-layer Pt-20Rh/T-11I/Pt-20Rh design, which rated next highest, was selected as the baseline design. The heat source, 0.984 in. in dia by 1.795 in. long, contains 33.1 watts of electrorefined PuO/sub 2/ and weighs 0.62 lb. A nonselective pressure relief device/capillary assembly is connected between the noble metal liner and clad to allow venting of the helium gas generated by fuel decay and also to allow decay of the generated radon-220 gas to allowable levels. Pressure relief device tests verified its flow stability and fuel fines retention capability. Radon attenuation tests indicated a 0.001-in. I.D. capillary is required to reduce the radon levels to acceptable levels if it is assumed that all generated radon is released from the fuel. Safety design verification tests, including granite impact, bullet impact, crushing, fire, and postaccident oxidation, indicated both the baseline and Hafnalloy designs to survive all accident environments except one by containing the fuel simulant in at least one totally integral capsule component. Neither design was capable of containing the fuel simulant under a 2000 ft-lb 30-06 rifle bullet impact. Further studies in this area as related to heat source design are required. (auth)
Date: April 1, 1973
Creator: Lurie, H.
Partner: UNT Libraries Government Documents Department

Nuclear-powered artificial heart prototype system development program. Quarterly progress report, April 1, 1976--June 30, 1976

Description: Research progress and accomplishments on the active program tasks (35-46) are reported. The tasks include thermal insulation and thermal protection; thermal converter; blood pump and power coupling; thermal and hydraulics; system integration and interfacing; IVBM system performance; IVBM system fabrications; added IVBM blood pump fabrication; IVBM system life testing; and reliability and quality assurance. (TFD)
Date: January 1, 1976
Partner: UNT Libraries Government Documents Department

Solubility study of strontium fuel compounds

Description: Strontium titanate, distrontium titanate, and strontium fluoride have been considered as isotopic fuels in thermoelectric generators for space and terrestrial applications. Evaluation of the radiobiological and radioecological effects of accidental release of /sup 90/Sr on land, in water, and in air requires a knowledge of the dissolution rates of the fuel in fresh water, salt water, and dilute HCl. Results of a study to investigate the behavior of these strontium fuel forms in the different test solutions are presented. (TFD)
Date: June 1, 1966
Creator: Gray, J. H.
Partner: UNT Libraries Government Documents Department

Mass spectrometric determination of $sup 18$O/$sup 16$O ratios to locate the source of oxygen in SNAP fuel capsule components

Description: The successful application of a mass spectrometric method to determine the source of oxygen diffusion into the container material of a radioisotopic fuel capsule is described. The source was chiefly the oxide fuel (/sup 238/PuO/ sub 2/) and not the atmosphere. This could be accomplished by determining the / sup 18/O//sup 16/O ratio in the tantalum alloy material, because the /sup 18/O content of the fuel had been reduced to minimize alpha -n reactions. The /sup 18/O//sup 16/O ratio was ~5.5 x 10/sup -4/ for fuel as compared with 2 x 10/sup - 3/ for air. The radiochemical method, based on an alpha -n reaction, could not be applied because of the very low alpha -particle flux in the liner material. (auth)
Date: February 1, 1974
Creator: Smith, M.E. & Waterbury, G.R.
Partner: UNT Libraries Government Documents Department

Characterization and modeling of the heat source

Description: A description of the input energy source is basic to any numerical modeling formulation designed to predict the outcome of the welding process. The source is fundamental and unique to each joining process. The resultant output of any numerical model will be affected by the initial description of both the magnitude and distribution of the input energy of the heat source. Thus, calculated weld shape, residual stresses, weld distortion, cooling rates, metallurgical structure, material changes due to excessive temperatures and potential weld defects are all influenced by the initial characterization of the heat source. Understandings of both the physics and the mathematical formulation of these sources are essential for describing the input energy distribution. This section provides a brief review of the physical phenomena that influence the input energy distributions and discusses several different models of heat sources that have been used in simulating arc welding, high energy density welding and resistance welding processes. Both simplified and detailed models of the heat source are discussed.
Date: October 1, 1993
Creator: Glickstein, S. S. & Friedman, E.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen