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Physical property measurements on NPR graphite. II. Unirradiated core graphite

Description: Four bars of NPR core graphite produced by the National Carbon Company were evaluated. Thermal conductivity, electrical resistivity, coefficient of thermal expansion, tensile strength, compressive strength, and modulus of rupture data are summarized. Statistical analysis of the data was carried out. It is demonstrated that anisotropy in the bars and the method of sampling affect the measured properties. TSX is shown to be more anisotropic than either CSF or TSGBF graphites used in the construction of some of the present Hanford reactors.
Date: August 29, 1961
Creator: Jackson, J.L.
Partner: UNT Libraries Government Documents Department

Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing

Description: Report issued by the APDA over a design study conducted on an "in-pile package loop for use as a reactor fuel test facility" (p. 5). The results are presented and discussed. This report includes tables, and illustrations.
Date: July 28, 1961
Creator: Blessing, W. G.; Balsbaugh, R. R.; Bloomfield, D. E.; Busch, J. S.; Hennig, R. J.; Jens, W. H. et al.
Partner: UNT Libraries Government Documents Department

Removal of Sodium from Core Subassemblies with White Oil and Ultrasonics

Description: Report issued by the APDA over methods "for removing sodium from fuel and blanket sub-assemblies that have been irradiated in the reactor of the Enrico Fermi Atomic Power Plant" (p. 3). The cleaning methods are described, as well as experimental studies conducted on them. This report includes illustrations, and photographs.
Date: 1961
Creator: Kanaan, Z. R. & Nash, C. R.
Partner: UNT Libraries Government Documents Department


Description: BS>The approach taken in measurements on the AGS experimental magnets is discussed, and results of various measurements are examined. Application of information to calibration of beam lenses is also mentioned. Graphs of several magnet properties are included. (D.C.W.)
Date: December 26, 1961
Creator: Danby, G.T.
Partner: UNT Libraries Government Documents Department

Helium Inleakage Through Porous-Walled Fuel Elements

Description: Theoretical and experimental studies indicated that the effective permeability coefficient for graphite is lowered by a helium stream in-sweeping through the graphite pores. This phenomenon was considered in the design of HTGR fuel elements. A portion of the helium gas which is drawn into each fuel element as a purge stream may enter through porous wall sections, supplementing the purge gas entering at the top of each fuel element. The purge stream leaves each fuel element through a header system which carries the purge gas to an external fission product trap. The flow rate through the trapping system determines the upper limit of the average in-leakage through the fuel element walls. In the case of the HTGR, a graphite having a helium permeability of 1.1 cm/sup 2//sec at 350 psia and 700 deg F (approximately 0.1 cm/sup 2//sec at 14.7 psia, 70 deg F) would result in 100% of the purge flow entering through the wall sections of the fuel element. A lower permeability graphite, with most of the purge flow entering at the top of the fuel element appeared to be more desirable for maintaining optimum purge flow conditions. (auth)
Date: November 21, 1961
Creator: Turner, R. F.
Partner: UNT Libraries Government Documents Department

Thermoelectric Nuclear Fuel Element Quarterly Progress Report, April-June 1961

Description: Uranium-bearing thermoelectric compounds are now being prepared by tantalum bomb melting and by the hydride process. Tests of devices made up from these compounds indicate that the main fabrication problems are densification and contact bonding. Data from a hot-swaged pellet and a swaged device of US/sub 2/ indicate some promise for that compound. Improvements in techniques of thermoelectric parameter measurements include programming of automatic test data recording at desired intervals around the clock; increased accuracy and versatility of measurements through use of a newly-constructed adjustable precision resistor; and a method for measuring which should lead to an experimental means for determining the thermoelectric figure of merit, Z. Potential profile studies on PbTe pelleta are yielding important information on contact resistance parameters. A fission-fired thermoelectric generator is being prepared for the next in-pile test. (auth)
Date: July 10, 1961
Partner: UNT Libraries Government Documents Department

The Calculation of Nonlinear Radiation Transport by a Monte Carlo Method

Description: A monte Carlo method of solving the one-dimensional equations of nonlinear radiation transport is compared with the Sn "characteristics" method of solution. It is concluded that the Monte Carlo method is accurate and stable and furthermore for a given time-cycle length and space-zone size the Monte Carlo method is more accurate than the Sn method.
Date: January 1, 1961
Creator: Fleck, J. A., Jr.
Partner: UNT Libraries Government Documents Department

Simulation of the Zirflex Process With an Analog Computer

Description: The Zirflex process was studied extensively at Hanford in the development of technology for the interim reprocessing of power reactor fuels. The process involves the dissolution of Zircaloy in aqueous ammonium fluoride - ammonium nitrate solution. It is of particular interest at Hanford because of the impending fuel recovery from Zircaloy-clad PRTR and NPR elements. The chemical kinetics of the Zirflex reaction were not fuily defined at the end of the original studies. However, a pseudo first order reaction with free'' fluoride (fluoride not complexed with Zr) was deemed to describe the kinetics adequately for engineering calculations. The refined kinetic equation and the analog computer solution on model of the system are discussed. The results of thirty computer simulated dis solutions are also presented, and the data are used to illustrate the effects of the process variables on the Zirflex dissolution time cycle. The data from a selected few of the runs are directly applicable to the reprocessing of PRTR fuel elements in Redox. It was found that the Zirflex reaction kinetics are dependent on free'' fluoride ion to the 2.0l7 power and on H ion to the 0.457 power according to laboratory data secured after completion of the original research and development studies. The direct integration of the kinetic equation was prevented by the complex interdependence of the chemical variables. However, an analog computer circuit was evolved which was used to solve the defining equations simultaneously. The circuitry is discussed in the report because of its applicability to future studies and its novel aspects. The data from the computer runs verified the results of the earlier laboratory and pilot plant work. However, a much clearer view of the process is presented with the continuous graphs of the variables prepared from the computer data. In addition, data not available from …
Date: October 25, 1961
Creator: Smith, P. W.
Partner: UNT Libraries Government Documents Department


Description: The formation, distribution, and biological effects of fallout are reviewed. Design features of structures for protection against fallout gamma radiation are described. Factors affecting gamma dose rate, shielding geometry, special shielding problems, and ventilation in shelters are discussed. Calculations are presented of the gamma dose from fallout for simple underground shelters, simple aboveground shelters, basement shelters, upper-story shelters, and compartmentalized structures. Charts for use in shielding calculations are included. (C.H.)
Date: October 1, 1961
Partner: UNT Libraries Government Documents Department

Positron Scanner for Locating Brain Tumors

Description: A system is described that makes use of positron emitting isotopes for locating brain tumors. This system inherentiy provides more information about the distribution of radioactivity in the head in less time than existing scanners which use one or two detectors. A stationary circular array of 32 scintillation detectors scans a horizontal layer of the head from many directions simultaneously. The data, consisting of the number of counts in all possible coincidence pnirs, are coded and stored in the memory of a Two-Dimensional Pulse- Height Analyzer. A unique method of displaying and interpreting the data is described that enables rapid approximate analysis of complex source distribution patterns. (auth)
Date: March 1, 1961
Creator: Rankowitz, S.; Robertson, J. S.; Higinbotham, W. A. & Rosenblum, M. J.
Partner: UNT Libraries Government Documents Department


Description: The addition of alloying elements to base alloys of Th containing 5 and 10 wt% U was investigated with regard to alloy structures and elevated- temperature mechanical properties. The alloys developed possess elevatedtemperature tensile and stress-rupture strengths of essentially twice those associated with binary Th-5 and 10 wt% U alloys at 60O to 800 deg C. The greater strength of these alloys should resuit in improved resistance to radiationinduced swelling at high temperatures. Noticeable improvement in elevated-temperature mechanical properties resulted from the addition of 2 and 5 wt% Zr to the Th-5 and Th-10 wt% U base alloys. Zr was found to be the most effective additive in improving elevated-temperature mechanical properties, although significant improvement was noted with additions of Nb, Mo, C, Al, and Be. Both solidsolution strengthening and dispersion strengthening of the Th --U base alloys were encountered. It was found that a fine intragranular distribution of the secondary U phase improved the mechanical properties of the alloys studied. Structures with optimum properties were produced by careful control of the arc-melting procedure and by solution heat treating at 1350 deg C followed by aging at 850 deg C. Preliminary testing was performed to determine the elevatedtemperature mechanical properties of Th metal and of the Th --U base alloys. Irradiation specimens of the most promising alloys were prepared. These specimens were encapsulated and are ready for irradiation testing at 800 deg C and for subjection to burnups of 10,000, 20,000 and 30,000 Mwd/ ton. (auth)
Date: November 1, 1961
Creator: Cole, R.H. & Wilkinson, L.E.
Partner: UNT Libraries Government Documents Department
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