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Effective Cadmium Cutoff Energies

Description: Effective cutoff energies for point l/v absorbers inside of spherical and cylindrical cadmium filters have been calculated for thermal reactor neutrons. The neutron spectrum was assumed to consist of a Maxwellian plus a 1/E component, and the parameters varied were the thickness of filter, the Maxwellian temperature and the Maxwellian to 1/E flux ratio. Because of the sensitivity of the effective cutoff to Maxwellian flux parameters for thin filters it is recommended that filter thicknesses of … more
Date: March 11, 1960
Creator: Stoughton, R.W.; Halperin, J. & Lietzke, M.P.
Partner: UNT Libraries Government Documents Department
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ELECTRON-SPIN-RESONANCE STUDIES ON PHOTO-SYNTHETIC MATERIALS

Description: A number of organisms have been examined for their ability to produce electron-spin-resonance signals at low temperatures in response to illumination. The efficiency of the response is of the order of not less than 5%, and the wavelength for maximum response is generally slightly on the longer side of the wavelength of maximum absorption, with a minimum appearing at the wavelength of maximum absorption.
Date: May 11, 1960
Creator: Sogo, Power B.; Carter, Louise A. & Calvin, Melvin.
Partner: UNT Libraries Government Documents Department
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Experience with anthracite - sand filters

Description: The General Electric Company operates eight large filter plants for the Atomic Energy Commission at the Hanford works in the state of Washington. Because of the importance of water to the process, research and development on water treatment has been an important part of the overall Hanford research and development program. The research and development on water treatment has resulted in important capital and operating savings and in the production of better quality water. It is the purpose of th… more
Date: November 11, 1960
Creator: Conley, W.R.
Partner: UNT Libraries Government Documents Department
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Further Development of Gas-Pressure Bonding of Zircaloy-Clad Flat-Plate Uranium Dioxide Fuel Elements

Description: The effects of core barrier coatings, void spaces, and surface-cleaning techniques on the quality of Zircaloyclad flat-plate UO/sub 2/ fuel elements prepared by gas-pressure bonding were investigated. Techniques were developed for the application of barrier layers of chromium by a vapordeposition process and of crystalline carbon by a pyrolytic process. These coatings, together with a graphite coating previously developed, were evaluated in pressure-bonded fuel elements for their effectiveness … more
Date: May 11, 1960
Creator: Paprocki, Stan J.; Hodge, Edwin S.; Layer, Edwin H.; Wintucky, Edwin G.; Gripshover, Paul J. & Carmichael, Donald C.
Partner: UNT Libraries Government Documents Department
open access

Irradiation effects on Zircaloy-2-uranium bonds

Description: The failure mechanics of high exposure, in-reactor coextruded fuel rods are quite different from those of defected unirradiated rods. The appearance and corrosion behavior of the high-exposure in-reactor failures suggests that the strength of the coextruded Zircaloy-2 to uranium bond has deteriorated. Notch-fracture tests, in which the strength of the Zircaloy-2 clad to uranium bond is evaluated in a qualitative manner, suggests that the bond strength has not deteriorated to the degree indicate… more
Date: April 11, 1960
Creator: Goffard, J. W.
Partner: UNT Libraries Government Documents Department
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Laboratory data for review of outlet water temperature limits for BDF type reactors

Description: A knowledge of the thermal and hydraulic conditions within a reactor fuel channel during an inadvertent flow reduction is needed to establish reactor operating limits. Such limits, which are based on outlet water temperature, are called ``trip-after-instability`` limits by the reactor operating personnel. Laboratory experiments were performed to update the knowledge of such conditions in a BDF reactor type fuel channel while using internally and externally cooled fuel elements (I&E`s) at tube p… more
Date: December 11, 1960
Creator: Waters, E. D. & Fitzsimmons, D. E.
Partner: UNT Libraries Government Documents Department
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LOSS-OF-PRESSURE ACCIDENT--HOT LEG PIPING FAILURE (BLOWER BEHAVIOR CONSIDERED)

Description: A study was made to determine pressure differentials across coolant system components by considering the blowers' influence during the transient state following a rupture in one hot leg of the Experimental Gas Cooled Reactor Coolant System. Results are presented in tables and graphs. It was concluded that a large instantaneous rupture of the reactor coolant system results in lifting the core when the entire graphite area is exposed to the differential. The forces depend on the type of gas … more
Date: January 11, 1960
Creator: Landoni, J. A.
Partner: UNT Libraries Government Documents Department
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Proposal for charging the third rupture fuel element experiment, GEH 12--16, 17, 18

Description: The objective of this irradiation is to verify the corrosion rate of a cluster-type fuel element under conditions of high specific power and central core temperatures. The test will also be used in the development of rupture detection instrumentation and decontamination procedures as a necessary part in the development of the NPR. In this test a fuel element irradiated to 3200 MWD/T will be ruptured, the rate of rupture product released will be determined and the gamma spectrum from fission pro… more
Date: January 11, 1960
Creator: Call, R. L. & Kaulitz, D. C.
Partner: UNT Libraries Government Documents Department
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PT-IP-364A: Fabrication of elements brazed closure, 1.6% enriched, 2 w/o zirconium core, KER size tube-tube elements (KAEA1)

Description: The test detailed in this report was designed to obtain irradiation data on the brazed closure on a tube-tube geometry. A 1.6% enriched, 2 w/o zirconium core was chosen for this test to gain a faster exposure rate. The brazing alloy for this test was composed of 84 Zry-2 + 4 Be + 12 Fe.
Date: November 11, 1960
Creator: Tverberg, J. C.
Partner: UNT Libraries Government Documents Department
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RADIATION SURVEY OF SIX OF THE THERMAL BARRIERS. CORE 1, SEED 1. Test Results T-643713

Description: A test was performed to determine the radiation levels of the thermal barriers contained in the rod-drive-mechanism housings. Of the six thermal barriers examined, the two-slot type instrumented barriers exhibited higher radiation levels (350 to 2450 mr/hr) than did either the plain type instrumented barrier (1350 mr/hr) or the three noninstrumented barriers (275 to 725 mr/hr). (W.L.H.)
Date: October 11, 1960
Partner: UNT Libraries Government Documents Department
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Recommended high-tank temperature for maintenance of high-tank backup support

Description: High tank line cleaning and low flow tests at B, D, F, and H Reactors have been completed and results analyzed and related to high tank backup support. Interim provisions have been completed at the old reactors for bleeding and temperature measurement of high tank cooling water. This letter supplies a recommended guide for maintaining high tank temperature control.
Date: October 11, 1960
Creator: Greager, O. H.
Partner: UNT Libraries Government Documents Department
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SNAP II REACTOR CORE MATERIALS

Description: A survey was made to select the construction materials for the SDR-1 reactor core vessel and grid plates. Hastelloy C was selected for the reactor vessel, top grid plate, and bottom grid plate. Inconel X was selected for the core hold-down springs. (C.J.G.)
Date: April 11, 1960
Creator: Facha, J. V.
Partner: UNT Libraries Government Documents Department
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SOME PHOTOCHEMICAL AND PHOTOPHYSICAL REACTIONS OP CHLOROPHYLL ANDITS RELATIVES

Description: The solution photochemistry of chlorophyll and chlorophyll analogs is described. Many cases of electron transfer to or from the porphyrin macrocycle have been found, but in no case has any very large degree of energy storage been achieved. Because of the very rapid back-reaction for products with a {Delta}F of approximately -30 kcal, some solid state models in which such an energy storage might be achieved are described and their possible relation to the natural photosynthetic apparatus is give… more
Date: April 11, 1960
Creator: Calvin, Melvin
Partner: UNT Libraries Government Documents Department
open access

Studies of Improvement of Power Density in Orr Loops

Description: Using a simplified model, calculations were made of the possible effects of voids upon the power density in ORR loop experiments. It is concluded that the power density may be markedly increased if voids and channels are plugged with moderator material such as graphite or beryllium. (auth)
Date: April 11, 1960
Creator: Tobias, M. L. & Vondy, D. R.
Partner: UNT Libraries Government Documents Department
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Study of Factors Influencing Ductility of Iron-Aluminum Alloys. Monthly Letter Report No. 9 for March 15, 1959 to March 15, 1960

Description: Initial heat-treatment studies are reported in which the effects of quenching rate upon room temperature ductility of iron-aluminum alloys were investigated. Quenching media included bciling water, oil at room temperature, and oil at 100 deg C. Experimental results are tabulated. No definite trends in tensile properties were observed with differences in quenching rate. Electropolishing techniques for use in preparation of specimens are discussed in relation to determination of microcrack effect… more
Date: January 11, 1960
Creator: Perkins, F. C. & Nachman, J. F.
Partner: UNT Libraries Government Documents Department
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A Study of the Fuel Value of U{Sup 23){Sup 3}

Description: The fuel value of U/sup 233/ was calculated for five thermal reactors (Dresden. Yankee, Carolinas-Vlrginia, Hallam, GCR-II). Relative to a U/sup 235/ value of per gram, pure U/sup 233/ had a value that varied from .2 to .2 per gram. U/sup 233/ contained in once- and twice-recycle uranium from an initial U/sup 233/-Th cycle had a value slightly in excess of the value of pure U/ sup 233.. The value of U/sup 233/ in recycle uranium from an initial U/sup 235/- Th cycle was less than that for pure U… more
Date: April 11, 1960
Creator: Jaye, S; Bennett, L L & Lietzke, M P
Partner: UNT Libraries Government Documents Department
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Supplement A production test IP-314-A, measurement of fuel element temperature changes as the result of film deposition

Description: The objective of this supplement is to determine the effects of operation with neutral pH water on crud deposition on fuel surfaces. This supplement authorizes testing designed to show the effects of coolant pH on the thickness of the crud layer deposited on fuel elements. The supplement will not require additional reactor down time nor will it introduce any hazards to the reactor.
Date: May 11, 1960
Creator: Miller, N. R. & Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Thermal conductivity studies on various calcined ``cold`` waste: Interim report

Description: Accelerated accumulation of high level radioactive wastes has given impetus to the development of safer and more economical waste storage methods. Several processes for converting these wastes to granular or porous-solid form are being investigated. In any waste volume-reduction process containment of the final material in a sealed metal shell is desirable as a precaution against accidental release of radioactive material. While the final waste forms are generally stable, they are, if uncontain… more
Date: March 11, 1960
Creator: DeMier, W. V.
Partner: UNT Libraries Government Documents Department
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