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Experiment DTA report for semiscale transparent vessel countercurrent flow tests

Description: Steady state air-water tests were performed as part of the Semiscale Blowdown and Emergency Core Cooling (ECC) Project to investigate downcomer countercurrent flow and downcomer bypass flow phenomena. These tests were performed in a plexiglass representation of the Semiscale pressure vessel which allowed changes to be madein the geometry of the upper annulus and downcomer for the purpose of investigating the sensitivity of downcomer and bypass flow to changes in system geometry. Tests were also performed to investigate the effects of two-phase inlet flows and different initial system pressures on countercurrent and bypass flow. Results for each test are presented in the form of computer printout of the measurements and of a summary of the pertinent calculated flow rates, pressures, and dimensionless volumetric fluxes. Descriptions of the test facility, instrumentation, operating procedures, and test conditions are also presented. An error analysis is presented for selected volumetric flux calculations. 10 references. (auth)
Date: October 1, 1975
Creator: Hanson, D.J.
Partner: UNT Libraries Government Documents Department

Decontamination and decommissioning of the EBR-I Complex. Final report

Description: This final report covers the Decontamination and Decommissioning (D and D) of the Experimental Breeder Reactor No. 1 (EBR-I) Complex funded under Contract No. AT(10-1)-1375. The major effort consisted of removal and processing of 5500 gallons of sodium/potassium (NaK) coolant from the EBR-I reactor system. Tests were performed to assess the explosive hazards of NaK and KO$sub 2$ in various environments and in contact with various contaminants likely to be encountered in the removal and processing operations. A NaK process plant was designed and constructed and the operation was successfully completed. Lesser effort was required for D and D of the Zero Power Reactor (ZPR-III) Facility, the Argonne Fast Source Reactor (AFSR) Shielding, and removal of contaminated NaK from the storage pit. The D and D effort was completed by 13 June 1975, ahead of schedule. (auth)
Date: July 1, 1975
Creator: Kendall, E.W. & Wang, D.K.
Partner: UNT Libraries Government Documents Department

Post treatment of high-level nuclear fuel wastes

Description: The glass-ceramic product prepared from fluidized-bed calcined synthetic commercial wastes, based on data obtained to date, has many of the properties desired for long-term storage. Although more characterization is necessitated, the product's high-calcine content will decrease the number of storage canisters required and use a minimum of product-forming additives, resulting in significant process cost savings. The product remains in a solid, nonflowing form at temperatures close to the preparation temperature and yet is prepared at relatively low temperatures. The product has void spaces to accommodate radiolytic gas formation, but is hard and dense and has very low leach rates. Process features, such as no direct product contact with furnace or storage canisters, will minimize corrosion of both process equipment and storage canisters. (auth)
Date: January 1, 1975
Creator: Berreth, J.R.; Cole, H.S.; Hoskins, A.P.; Lewis, L.C. & Samsel, E.G.
Partner: UNT Libraries Government Documents Department

Transient three-dimensional thermal-hydraulic analysis of nuclear reactor fuel rod arrays: general equations and numerical scheme

Description: A mathematical model and a numerical solution scheme for thermal- hydraulic analysis of fuel rod arrays are given. The model alleviates the two major deficiencies associated with existing rod array analysis models, that of a correct transverse momentum equation and the capability of handling reversing and circulatory flows. Possible applications of the model include steady state and transient subchannel calculations as well as analysis of flows in heat exchangers, other engineering equipment, and porous media. (auth)
Date: November 1, 1975
Creator: Wnek, W.J.; Ramshaw, J.D.; Trapp, J.A.; Hughes, E.D. & Solbrig, C.W.
Partner: UNT Libraries Government Documents Department

Fast neutron spectrum and dosimetry studies in the Coupled Fast Reactivity Measurements Facility

Description: The fast neutron spectrum of the Coupled Fast Reactivity Measurements Facility (CFRMF) at the Idaho National Engineering Laboratory (INEL) is being used to study and standardize fast reactor neutron dosimetry materials and methods. The CFRMF has been designated a ''benchmark experiment'' to test the cross section data of dosimetry materials as well as other materials used and produced in fast reactors. Information about the neutron energy spectrum of the CFRMF is presented. (auth)
Date: January 1, 1975
Creator: Rogers, J.W.; Harker, Y.D. & Millsap, D.A.
Partner: UNT Libraries Government Documents Department

Radioactive-nuclide decay data in science and technology

Description: The scope of ENDF/B has recently been expanded to include radioactive- nuclide decay data. In this paper, the content and organization of the decay data which are included in ENDF/B are presented and discussed. The application of decay data in a wide variety of nuclear-related activities is illustrated by a number of examples. Two items pointed up by the ENDF/B decay-data compilation effort are treated: the identification of deficiencies in the data; and the importance of a radioactive-nuclide metrology effort oriented toward supplying these needs in a systematic fashion. (3 figures, 1 table) (auth)
Date: January 1, 1975
Creator: Reich, C.W. & Helmer, R.G.
Partner: UNT Libraries Government Documents Department

Remote acquisition of gamma-ray pulse height spectra

Description: The acquisition of pulse height spectra data in the industrial environment has traditionally evolved along two paths. The first required the transporting of a radioactive sample from the place of production to a computer system for counting and analysis. This method results in a degradation of the data due to the time delay between sample production and subsequent counting. The second path was taken to count the sample at the place of production and transport the data in the form of paper or magnetic tape to a computer for analysis. Automation of the traditional methods is usually impractical. This paper describes two methods of remote data acquistion developed at the Idaho National Engineering Laboratory which were formulated to mechanize the complete process from data gathering to analysis. Both methods utilize voice grade telephone links between the data gathering device and a PDP-9 computer. The two methods differ in the type of device used to acquire the data. The first is a completely hardwired system. The second is a computer based system utilizing a PDP-8/E. Differences between the two systems are described and evaluations made as to cost versus versatility. (auth)
Date: January 1, 1975
Creator: Killian, E.W. & Heath, R.L.
Partner: UNT Libraries Government Documents Department

Integral capture cross-section measurements in the CFRMF for LMFBR control materials

Description: Integral capture-cross sections for separated isotopes of Eu and Ta are reported for measurements in the Coupled Fast Reactivity Measurements Facility (CFRMF). These cross sections along with that measured in the CFRMF for $sup 10$B(n,$alpha$) provide an absolute standard for evaluating the relative reactivity worth of Eu$sub 2$O$sub 3$, B$sub 4$C and Ta in neutron fields typical of an LMFBR core. Based on these measurements and for neutron fields characterized by the $sup 235$U:$sup 238$U reaction rate spectral index ranging from 23 to 50, the infinitely dilute relative worth of Eu$sub 2$O$sub 3$ has been estimated to be 25 to 40 percent higher than that for B$sub 4$C and 80 percent to 100 percent higher than that for Ta. 11 references. (auth)
Date: January 1, 1975
Creator: Anderl, R.A.; Harker, Y.D.; Turk, E.H.; Nisle, R.G. & Berreth, J.R.
Partner: UNT Libraries Government Documents Department

Manganese bath systematic effects in measurements of nu-bar and eta

Description: Measurements using the manganese bath technique are central to the discrepancy that has existed between measured values of $nu$-bar for $sup 252$Cf. Manganese bath measurements of $nu$-bar belong to the lower group of values, while the eta measurements are consistent with the higher $nu$-bar values. A three-part study was performed to see if the discrepancy could be explained by differences in manganese bath techniques: (1) A $sup 252$Cf source previously calibrated by De Volpi was calibrated in the MTR manganese bath; (2) The recommendations made by De Volpi for altering the MTR eta values were carefully considered; and (3) The results of the Monte Carlo calculation of the MTR experiments, carried out at Bettis Atomic Power Laboratory, were examined in detail. The study produced insignificant changes in the eta values. (6 tables) (auth)
Date: January 1, 1975
Creator: Smith, J.R.
Partner: UNT Libraries Government Documents Department

Multiple-task real-time PDP-15 operating system for data acquisition and analysis

Description: The RAMOS operating system is capable of handling up to 72 simultaneous tasks in an interrupt-driven environment. The minimum viable hardware configuration includes a Digital Equipment Corporation PDP-15 computer with 16384 words of memory, extended arithmetic element, automatic priority interrupt, a 256K-word RS09 DECdisk, two DECtape transports, and an alphanumeric keyboard/ typer. The monitor executes major tasks by loading disk-resident modules to memory for execution; modules are written in a format that allows page-relocation by the monitor, and can be loaded into any available page. All requests for monitor service by tasks, including input/output, floating point arithmetic, request for additional memory, task initiation, etc., are implemented by privileged monitor calls (CAL). All IO device handlers are capable of queuing requests for service, allowing several tasks ''simultaneous'' use of all resources. All alphanumeric IO (including the PC05) is completely buffered and handled by a single multiplexing routine. The floating point arithmetic software is re-entrant to all operating modules and includes matrix arithmetic functions. One of the system tasks can be a ''batch'' job, controlled by simulating an alphanumeric command terminal through cooperative functions of the disk handler and alphanumeric device software. An alphanumeric control sequence may be executed, automatically accessing disk-resident tasks in any prescribed order; a library of control sequences is maintained on bulk storage for access by the monitor. (auth)
Date: January 1, 1974
Creator: Myers, W.R.
Partner: UNT Libraries Government Documents Department

Evaluated decay-scheme data for the ILRR program

Description: The half-lives and $gamma$-ray intensities associated with radioactive decay have been evaluated for nuclides of interest to the Interlaboratory LMFBR Reaction Rate program. The results indicate that for most of the isotopes the decay parameters are known sufficiently well to meet the ILRR goals of 2$sup 1$/ $sub 2$ or 5 percent accuracy in reaction rate measurements. (auth)
Date: January 1, 1975
Creator: Helmer, R.G. & Greenwood, R.C.
Partner: UNT Libraries Government Documents Department

MATPRO: a handbook of materials properties for use in the analysis of light water reactor fuel rod behavior

Description: This handbook describes the materials properties correlations and computer subcodes (MATPRO) developed for use with various LWR fuel rod behavior analytical programs at the Idaho National Engineering Laboratory. Documentation and formulations that are generally semiempirical in nature are presented for uranium dioxide and mixed uranium-plutonium dioxide fuel, zircaloy cladding, gas mixture, and LWR fuel rod material properties.
Date: February 1, 1976
Creator: MacDonald, P. E. & Thompson, L. B. (eds.)
Partner: UNT Libraries Government Documents Department

Analysis of the binary cycle for geothermal power generation

Description: Exchanging heat from hot geothermal fluid to a secondary working fluid which is then expanded through a turbine appears to be the best way of producing electrical power from a medium temperature geothermal resource. A study has been made to determine the conceptual design state points for a dual boiling system which utilizes isobutane as the working fluid. The results of this work and the sensitivity of plant performance to variations from nominal design points are presented. In addition, variations due to tolerances applied to thermodynamic properties and other key factors are included. (auth)
Date: December 1, 1975
Creator: Madsen, W. W. & Ingvarsson, I. J.
Partner: UNT Libraries Government Documents Department

Conceptual study for total utilization of an intermediate temperature geothermal resource

Description: A multi-use, integrated project plan has been developed for the combined electrical and direct utilization of an intermediate temperature geothermal resource. This concept addresses an integrated project plan with industrial participation, which could make a significant contribution to the national plan for energy independence, by creating new and realistic energy choices for the immediate future.
Date: April 1, 1976
Creator: Swink, D. G. & Schultz, R. J.
Partner: UNT Libraries Government Documents Department

LOFT data acquisition and visual display system (DAVDS) presentation program

Description: The Data Acquisition and Visual Display System (DAVDS) at the Loss-of-Fluid Test Facility (LOFT) has 742 data channel recording capability of which 576 are recorded digitally. The purpose of this computer program is to graphically present the data acquired and/or processed by the LOFT DAVDS. This program takes specially created plot data buffers of up to 1024 words and generates time history plots on the system electrostatic printer-plotter. The data can be extracted from two system input devices: Magnetic disk or digital magnetic tape. Versatility has been designed in the program by providing the user three methods of scaling plots: Automatic, control record, and manual. Time required to produce a plot on the system electrostatic printer-plotter varies from 30 to 90 seconds depending on the options selected. The basic computer and program details are described.
Date: March 1, 1976
Creator: Bullock, M. G. & Miyasaki, F. S.
Partner: UNT Libraries Government Documents Department