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A SUMMARY OF INDUSTRIAL ACCIDENTS IN USAEC FACILITIES
The accident experience of the AEC contractor operation for 1959 and 1960 is reported. Incidents involving radio active materials are described. A table of inadvertent criticality was included to supplement other tables. A tabulation of exposure records at values from 0 to 15 r is given. (M.C.G.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
CALCULATION OF THE REQUIREMENTS FOR OPERATION OF REFRACTORY-METAL COMPONENTS AT HIGH TEMPERATURE IN VACUUM
Equations based on kinetic theory relate the contamination of refractory metals in vacuum to the appropriate variables. Several examples are given for which the allowable system pressures are calculated. The examples illustrate the effect of varying several parameters. The importance of the sticking factor for active gases on hot refractory metals and its effect on the system design are discussed. The data for estimating the sticking factor for O/sub 2/ on Nb are given, along with some estimated values. Experimental data on the composition and rates of outgassing of ultrahigh-vacuum systems and their importance in system design are discussed. Several methods of reducing contamination rates and the relative ease and effectiveness of these methods are presented. It was concluded that tests of 1000 hr or longer will probably require system pressures of between 10/sup -9/ and 10/sup -6/ torr, the particular pressure depending upon the residual gas composition, test duration, allowable contamination level, and the other variables discussed. Since the most important source of contamination in a properly designed ultrahigh-vacuum system is the outgassing process, bakeable systems should be designed to operate with walls as cool as practical, and to have a minimum of surface area and outgassing materials inside. …
Date:
September 18, 1962
Creator:
Clausing, R.E.
Object Type:
Report
System:
The UNT Digital Library
NUCLEAR SUPERHEAT PROJECT TENTH QUARTERLY PROGRESS REPORT, OCTOBER-DECEMBER 1961
Results in the Nuclear Superheat Project are summarized. Topics covered include: conceptual design and program evaluation, fuel technology, materials development, experimental physics, coolant chemistry, heat transfer, mechanical development, SADE and E-SADE, and mixed spectrum superheat study. (M.C.G.)
Date:
October 31, 1962
Creator:
Pennington, R.T.
Object Type:
Report
System:
The UNT Digital Library
EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report No. 3, April-June 1961
The heat-transfer loop was completed and is in operation. Difficulty was experienced in obtaining a sufficiently strong connection between the burnout- detector voltage tap and the heating element. This problem and its potential solution are described. The lack of means of obtaining controlled burnout prevented collection of data on the burnout effects of the ultrasonic field. (auth)
Date:
October 31, 1962
Creator:
Romie, F.E.
Object Type:
Report
System:
The UNT Digital Library
The Measurement of Energy and Intensity of Gamma Rays by Use of a Scintillation Spectrometer
The analysis of gamma-ray spectra measured with a scintillation counter with an anticoincidence annulus is described in detail. In particular the problem of the determination of the energy and intensity of gamma rays from such measurements is considered. The shapes of the full-energy peaks in observed complex spectra are studied and an attempt is made to justify their description in terms of a Gaussian response function. The details of the statistical analysis of complex gamma-ray spectra are given and, finally, procedures which have been used to confirm the validity of error estimates in energy and intensity measurements are described. (auth)
Date:
April 1, 1962
Creator:
Julke, R. T.; Monahan, J. E.; Raboy, S. & Trail, C. C.
Object Type:
Report
System:
The UNT Digital Library
SOLUBLE NEUTRON POISONS AS A PRIMARY CRITICALITY CONTROL IN SHIELDED AND CONTAINED RADIOCHEMICAL FACILITIES
Studies indicated that the use of soluble poisons as a primary criticality control offers economic and other advantages in that it permits the factors of vessel size and shape and solution concentrations to be dictated by considerations other than those of criticality. It is believed that soluble poison criticality control can be made as reliable as other methods of coaditional control if the application is preceded by adequate development work and is monitored by multiple. independent safeguards. The studies included multigroup machine calculations of the required content of poisons in solutions of fissile and fertile material, a compilation of data on the detection, stability, decontamination, and costs of soluble poisons, and an assessment of the possible effects of a nuclear excursion. (auth)
Date:
July 26, 1962
Creator:
Nichols, J.P.
Object Type:
Report
System:
The UNT Digital Library
THE DEVELOPMENT OF A SUMP-TYPE SOLIDIFIED-METAL SEAL
A solidified-metal seal for possible use in moIten-saIt systems was fabricated and tested on a laboratory scale/su The seal consisted of an 80 Au-20 Cu (wt%) sealant alloy in contact with IN0R-8 base metal/su Eleven successive helium-leak-tlght sealings were effected before termination of the test due to a leak in one of the mating parts/su With better control over the heating cycle and slight modifications in seal design, it is expected that the useful life of a seal of this type could be extended even further. (auth)
Date:
March 15, 1962
Creator:
Donnelly, R.G.
Object Type:
Report
System:
The UNT Digital Library
Criteria for the Design of the Thorium Fuel Cycle Development Facility
Criteria for the conceptual design of the proposed Thorium Fuel Cycle Development Facility to be located at the Oak Ridge National Laboratory were established and are presented. In addition, conceptual layouts of the building and equipment are included. Reference fuel elements and processes that were selected as a basis for developing criteria for the facility are described. (auth)
Date:
March 1, 1962
Creator:
Irvine, A.R. & Lotts, A.L.
Object Type:
Report
System:
The UNT Digital Library
APPLICATIONS OF SNAP REACTOR SYSTEMS TO COMMUNICATIONS SATELLITES
Methods are presented for determining the electric power requirements of a given communications mission in terms of mission and orbit parameters. Analyses were made of possible applications of available and projected space auxiliary power units in these satellites. The satellitc as a communication node is discussed. Example calculations are given. (M.C.G.)
Date:
July 30, 1962
Creator:
Wimmer, R.E.
Object Type:
Report
System:
The UNT Digital Library
KINETIC EXPERIMENTS ON WATER BOILERS-"A" CORE REPORT-PART II. ANALYSIS OF RESULTS
The status of the analytic portion of the KEWB program at the time of completion of the spherical core experiments is summarized. Three computer programs were developed for use in this analytic effort. The first reassembles and smooths three decades of reactor power data read separately from oscillogram records of reactor excursions. It then computes the logarithmic derivative of the power, energy release, fuel solution temperature, and temperature compensated reactivity. The second program utilizes the space-independent neutron kinetics equations with any number of delayed neutron groups to determine the reactivity in the reactor from the power and its derivative. The third program solves the space-independent kinetics equations for the neutron flux from an input reactivity or initial period. Up to 50 reactivity feedback equations includirg delayed neutrons are provided for in this program. A mathematical model of the reactor investigated extensively was one containing six delayed neutron groups, conventional treatment of temperature reactivity compensation, and void compensation of reactivity induced by radiolytic gas void growth proportional to the product of reactor power and energy release. Partial mathematical solutions to the kinetic equations were derived for reactivity feedback proportional to prompt temperature and void growth according to the product of power …
Date:
February 1, 1962
Creator:
Dunenfeld, M. comp.
Object Type:
Report
System:
The UNT Digital Library
Corrosion Behavior of Reactor Materials in Fluoride Salt Mixtures
Molten fluoride salts, because of their radiation stability and ability to contain both Th and U, offer important advantages as high-temperature fuel solutions for nuclear reactors and as media suitable for nuclear fuel processing. Both applications have stimulated experimental and theoretical studies of the corrosion processes by which molten salt mixtures attack potential reactor materials. Corrosion experiments with fluoride salts which were conducted in support of the Molten-Salt Reactor E xperiment and analytical methods employed to interpret corrosion and masstransfer behavior in this reactor system are discussed. The products of corrosion of metals by fluoride melts are soluble in the molten salt; accordingly passivation is precluded and corrosion depends directly on the thermodynamic driving force of the corrosion reactions. Compatibility of the container metal and molten salt, therefore, demands the selection of salt constituents which are not appreciably reduced by useful structural alloys and the development of container materials whose components are in near thermodynamic equilibrium with the salt medium. Utilizing information gained in corrosion testing of commercial alloys and in fundamental interpretations of the corrosion process, an alloy development program was conducted to provide a high temperature container material that combined corrosion resistance with useful mechanical properties. The program …
Date:
September 19, 1962
Creator:
DeVan, J. H. & Evans, R. B., III
Object Type:
Report
System:
The UNT Digital Library
Measurements and Changes on SM-1 Core II During Period October 1, 1961 to May 30, 1962
Tests at the SM-1 reactor are reported for the period October 1, 1961, to May 31, 1962. Loading changes were made in SM-1 Core II during the scheduled semiannual shutdowns in October to November 1961 and April to May 1962. Core physics tests include control rod bank calibrations, bank position at several temperature and xenon poison conditions vs core changes and energy release, shutdown neutron source decay and startup channel testing, and critical rod positions for stuck rod configurations. Shielding measurements of gamma radiation in the rod drive pit were made, and dose rates from spent fuel elements as a function of the depth of the water shield were obtained. A lift mechanism for the BF/sub 3/ detector of one startup channel was installed and preliminary testing completed. Water chemistry and radiochemistry tests included a changeover to high pH for the primary coolant, fission product monitoring for iodine, measurement of dose rates on primary system during shutdown, radiochemical analysis of primary water and crud, and change of metal corrosion samples. Buildup of radioactivity in the demineralizer was monitored by radiation surveys and film badge exposures. (auth)
Date:
July 1, 1962
Creator:
Motte, F. G.; Best, W. C. & Kortheuer, J. D.
Object Type:
Report
System:
The UNT Digital Library
Snap Shield Test Experiment Reactor Physics Tests
The initial physics tests on the Shield Test Experiment reactor and the precriticality rod-drop test data are presented. (auth)
Date:
July 15, 1962
Creator:
Tomlinson, R. L.; Johnson, R. P. & Wogulis, S. G.
Object Type:
Report
System:
The UNT Digital Library
Emission Characteristics of Tantalum, Tungsten, Rhenium, and Iridium in Plasma Diodes
Experimental determinations of the ionic and electronic emission characteristics of Ta, W, Re, and lr cathodes in vapor thermionic converters are compared. It is shown that Ta provides superior thermal ionization qualities at high pressure compared with W, Re, and Lr. High electronic current densities may be obtained from Cs on Re and Cs on Ir at much lower Cs vapor pressures than from Ta or W. An over-all efficiency of 19% was achieved with a Re cathode at 2440 deg K. (auth)
Date:
March 15, 1962
Creator:
Gust, W. H.
Object Type:
Report
System:
The UNT Digital Library
CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JULY, AUGUST, SEPTEMBER, 1961
Development activities are reported on pyrometallurgical processes including melt refining and those using liquid metal solvents. Development of processing facilities for EBR II is also reported. In other work, laboratory- and engineering-scale investigations on fluoride volatility processes were condueted, and conversion of UF/sub 6/ to UO/sub 2/ was studied. Investigations are also reported concerning the kinetics of metal ignition and oxidation, and metalwater reactions. In work associated with reactor chemistry, data on nuclear constants are reported and developments in thermoelectricity and reactor decontamination are described. (J.R.D.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
CORE A CRITICAL STUDIES FOR THE ENRICO FERMI ATOMIC POWER PLANT ON ZPR-III
A critical studies program for the Enrico Fermi Atomic Power Plant was run with the ZPR-III fast critical facility. The objectives of this program included determination of the U enrichment required for criticality, the effect of minor variations in core and blanket composition, reactivity coefficients, control and safety rod characteristics, power distribution, spectral indices, and the reactivity worth and wave shape of the oscillator rod. The experimental program was separated into two phases. The first phase involved investigatlona of a clean assembly, which was a simplified and homogenized core and blanket geometry constructed for ease of experimental manipulation and analysis. The second phase involved experiments on the engineered, or as-designed, core. This assembly included such engineering details as control and safety rod channels, core end gaps, and a precise reconstruction of the core outline. This provided detailed information on worths of control rods and fuel subassemblies, power distribution, and the effect of variations in core and end-gap dimensions. The application of critical experiment data to the determination of the Enrico Fermi reactor characteristics has established the U/sup 235/ enrichment for the fuel alloy, worths of fuel subassemblies, and the B/sup 10/ enrichment for the control and safety rods. In addition, …
Date:
October 1, 1962
Creator:
Branyan, C.E.
Object Type:
Report
System:
The UNT Digital Library
PHYSICS ANALYSIS OF THE JUGGERNAUT REACTOR
The JUGGERNAUT is an intermediate-power research reactor designed and constructed as a supporting facility for chemistry and physics research. The design of this reactor is similar to that of the ARGONAUT, and those methods of evaluating the nuclear characteristics of the ARGONAUT which gave good agreement with experimental data were considered applicable to the analysis of the JUGGERNAUT. The analyses for both the JUGGERNAUT and the ARGONAUT were based on a modified two-group theory. The criticality calculations were carried out with the 1BM704 and the two-dimensional PDQ code. Reactivity effects were calculated by hand by means of perturbation techniques, with the real and adjoint fluxes obtained from PDQ calculations. (J.R.D.)
Date:
July 1, 1962
Creator:
Moon, D.P.
Object Type:
Report
System:
The UNT Digital Library
2D PERT. A TWO-DIMENSIONAL PERTURBATION CODE
Given multigroup fluxes and adjoint fluxes of any cylindrical R-Z configuration, 2D PERT may compute: the prompt-neutron lifetime; the relative worth of various delayed neutrons; the integrals of capture, fission, etc., of given materials over any given region; local perturbations, i.e., danger coefflcients; and integrated perturbations, i.e., reactivity effect of uniform variation in the cross sections affecting a whole region. 2D PERT is programmed for a 32K IBM-704 using 3 tape units. The code is written in FORTRAN with the exception of two SAP subroutines. Input fluxes and adjoint fluxes are on tapes which may be obtained either directly from CUREM output or manufactured by a special tape-writing routine. Homogeneous cross sections and variations of these cross sections are either read in as input information or are computed by the code from a microscopic-cross-section library and atomic densities given as input. A combination of these methods may be used. (auth)
Date:
May 1, 1962
Creator:
Chaumont, J. M. & Koerner, J. A.
Object Type:
Report
System:
The UNT Digital Library
EQUIPOISE 3A
None
Date:
June 1, 1962
Creator:
Nestor, C. W. Jr.
Object Type:
Report
System:
The UNT Digital Library
THE THEORY AND MEASUREMENT OF CRITICALITY
ABS>The measurable properties of a critical assembly (e.g.. fission, capture, and leakage rates; neutron-per-fission ratios; bare/Cd-covered reaction rate of-atios; danger eoefficients; etc.), whose judicious use completely defines tbcneutron economy in the assembly, are discussed. Require ments regarding the internal consisteney of these of:deasured quantities are reviewed. lt is concluded that theoretical analysis of the assembly must both reproduce the gross experimental results and reflect the internal consistency of the data. Only thermal systems fueled with U/sup 235/ and U/sup 238/ are considered. (T.F.H.)
Date:
January 1, 1962
Creator:
Kelber, C.N.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Heat Rejection Systems for PL-3
An investigation was made of heat rejection systems for use in the PL-3 nuclear power plant, designed for placement at Byrd Station, Antarctica. It was concluded that the glycol-coupled surface condenser and air blast cooler combination appears to be suited for PL-3 plant requirements and operating conditions. (auth)
Date:
March 1, 1962
Creator:
Thurnau, C. J.
Object Type:
Report
System:
The UNT Digital Library
SNAP Radioisotope Space Programs Quarterly Progress Report No. 9, October 1 Through December 31, 1961
All Phase I and Phase II testing was completed. Both launches of Phase I were successful, neither Phase II launches were successful. Test data recovered on Phase I launchings included optical coverage of re-entry and the trajectory and weather data; no telemetry canister temperature data were obtained. No test data were obtained on Phase II experiments. Reduction of Phase I test data was begun. The Phase II (Sub-subtask 7.3.2) was terminated December 20, 1961, when no test data were recovered for comparison with the analytically predicted results. The Sub-subtask 7.3.3 program (Generator Re-entry Burnup Study) was completed and terminated December 29, 1961. The study objectives were met. The Sub-subtask 7.3.4 program (High Altitude Sampling) was terminated when it was completed November 30, 1961. All study objectives were met. Topical reports were prepared on Sub-subtasks on the work performed in the reporting period that was not included in the topical reports is included. Checkout and troubleshooting operations on the last two subroutines and main radioisotope shielding code were completed. Results from several runs of a simple check problem compared well with published data. (auth)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
COMPILER INTO GEORGE ASSEMBLY ROUTINE
This program of the GEORGE Assembly Routine (GAR) will accept Fortran- like statements from paper tape and create the GAR language program on tape. This includes the needed calls for common subroutines and the reservations for the named variables and temporaries. The original statements in Fortran are carried along as remarks. The GAR language program may then be processed in the usual way by the GEORGE Assembly Routine, giving machine-language code. The level of sophistication of the source language is roughly equal to that of Fortransit or SALT. (auth)
Date:
June 1, 1962
Creator:
George, R.
Object Type:
Report
System:
The UNT Digital Library
EQUIPOISE-3: A TWO DIMENSIONAL, TWO-GROUP, NEUTRON DIFFUSION CODE FOR THE IBM-7090 COMPUTER
EQUIPOISE-3 is an IBM-7090 FORTRAN programmed code for the solution of two-group, two-dimensional, neutron diffusion equations. A maximum of 2l00 mesh points may be used, and the code will solve problems in either rectangular or cylindrical geometry. Logarithmic derivative boundary conditions are allowed, and removal of neutrons from both groups is permitted. Adjoint fluxes with the associated fluxadjoint flux regional integrals may be calculated automatically if desired. A constant buckling, group-dependent buckling, or region-dependent buckling may be specified for rectangular geometry. This program is intended to fill the need for a rapid two-dimensional calculation suitable for survey calculations. During the iterative part of the computations, all operations are carried out in the core memory. The magnetic tape memory is used only for input, output, and program storage. The running time for a 1000-point problem requiring 100 iterations would be about 3 min.(auth)
Date:
February 21, 1962
Creator:
Fowler, T.B. & Tobias, M.L.
Object Type:
Report
System:
The UNT Digital Library