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Thermal Test Unit

Description: Report discussing a performance evaluation of the Thermal Test Unit, a piece of test equipment fabricated to "aid the Hanford Works in experimentally determining heat transfer characteristics for a particular application."
Date: May 31, 1950
Creator: Cohen, A. & Rede, G. R.
Partner: UNT Libraries Government Documents Department
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In-reactor rupture testing of Zircaloy-2 clad seven-rod cluster fuel elements

Description: Three tests have been run in the ETR in high temperature, high pressure, recirculating water. In one test, previously unirradiated fuel elements were used and in the other two the fuel was irradiated to 2400 MWD/T at HAPO prior to insertion in the ETR. Failure was initiated by shearing off a projection on the surface of one rod of a fuel element, thus opening a 25-mil hole through the cladding. The projection was sheared off by a hydraulically operated chisel controlled from outside the reactor… more
Date: April 15, 1960
Creator: Call, R. L. & Kaulitz, D. C.
Partner: UNT Libraries Government Documents Department
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In-reactor rupture testing of Zircaloy-2 clad seven-rod cluster fuel elements: Interim report

Description: The high pressure loop installed in the 3X3 reflector position of the ETR and the associated instrumentation to detect and study failure mechanisms handled the rupture tests without difficulty. Failure of the elements was initiated by shearing off a projection on the fuel elements. The first test of the series used previously unirradiated seven-rod clusters. After the projection was sheared off the fuel elements were operated for seven hours with no failure. Failure is defined as having occurre… more
Date: May 3, 1960
Creator: Call, R. L.; Green, J. W. & Kaulitz, D. C.
Partner: UNT Libraries Government Documents Department
open access

Testing of Zircaloy-2-Clad Uranium Seven-Rod Fuel Elements. Final Report

Description: In 1955 the Fuels Development Operation began irradiation testing of fuel elements in high temperature water. It was assumed that if a new reactor were built at Hanford, it would be cooled by high-temperature, pressurized water. Corrosion tests showed that aluminum-clad production fuel elements could not be used in high-temperature water. Therefore, while work to improve the resistance of aluminum to high-temperature water proceeded, the Fuel Design Operation began irradiation of stainless stee… more
Date: July 5, 1960
Creator: Geering, G. T.
Partner: UNT Libraries Government Documents Department
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Beryllium Reflector Specimen Thread Strength Tests

Description: Strengths at failure are reported for a number of threaded beryllium specimens loaded in tension at room temperature and -320 degrees F. Loads greater than normal bolt strengths were repeatedly carried. The standard fine thread was somewhat stronger than the standard coarse thread. Material at the entrance of the hole should be counter-bored about one diameter deep in order to resist cone-type fracture. Pure tensile loading should be used. Possible shear loading should be carried by separate pi… more
Date: May 1, 1963
Creator: Kallin, I. N.
Partner: UNT Libraries Government Documents Department
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Core Band Tensile Test

Description: This test was conducted to determine the adequancy of the Core Band to withstand the forces imposed upon it during Reactor Operation.
Date: January 13, 1964
Creator: Allison, H. & Zibritosky, G.
Partner: UNT Libraries Government Documents Department
open access

Abstract -- A description of low temperature hydriding of zircaloy at Hanford

Description: The two K Reactors at the Hanford Plant of the Atomic Energy Commission were retubed in 1963 with ribless Zircaloy process tubes. These tubes, 1.81 inch OD x 0.037 inch wall, were made by tube reducing methods from extruded blooms and were installed without final pickling or autoclaving. These tubes are used with once-through filtered water with a maximum coolant temperature of approximately 110 C. After approximately two years` service, it was discovered that these tubes were absorbing hydroge… more
Date: March 31, 1966
Creator: Alexander, W. K.
Partner: UNT Libraries Government Documents Department
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Aerospace nuclear safety report for August 1967

Description: The AEC Safety Branch advised that the present outlook for a potential mission using four modified SNAP-3 type generators is rather negative. Drop tests of four SNAP-19 intact reentry heat source capsules were conducted at the Tonopah Test Range. A preliminary GE SNAP-27 safety analysis was reviewed. Three arc tunnel tests were conducted at low heat fluxes. Debris were collected on downrange impactors from all tests. The rapid helium depressurization test on fuel microspheres was conducted by B… more
Date: September 1, 1967
Creator: Illing, R.G. (comp.)
Partner: UNT Libraries Government Documents Department
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Characterization of the eastern gas shales

Description: The outgassing characteristics of the shale are being investigated using gas chromatography and mass spectrometry. An extensive geochemical characterization of the samples is also being performed. This characterization includes the identification of secondary resources. Mechanical testing and mass spectrometry have been integrated to provide some insight into the mechanical properties of the shale and gas released from the shale as a function of newly exposed surface area. Mechanical tests are … more
Date: unknown
Creator: Zielinski, R.E.
Partner: UNT Libraries Government Documents Department
open access

Failure analysis of radioisotopic heat source capsules tested under multi-axial conditions

Description: In order to qualify small radioisotopic heat sources for a 25-yr design life, multi-axial mechanical tests were performed on the structural components of the heat source. The results of these tests indicated that failure predominantly occurred in the middle of the weld ramp-down zone. Examination of the failure zone by standard metallographic techniques failed to indicate the true cause of failure. A modified technique utilizing chemical etching, scanning electron microscopy, and energy dispers… more
Date: unknown
Creator: Zielinski, R. E.; Stacy, E. & Burgan, C. E.
Partner: UNT Libraries Government Documents Department
open access

Thulium oxide fuel characterization study: Part 3, Procedures. [Tm/sub 2/O/sub 3/-Yb/sub 2/O/sub 3/]

Description: Procedures are presented for the following: Tm/sub 2/O/sub 3/-Yb/sub 2/O/sub 3/ pseudo - binary phase diagram tests; compatibility tests; thulium-170 oxide dose rate measurements; preparation of Tm/sub 2/O/sub 3/ wafers; SRL thulium and/or ytterbium oxide powder reprocessing for sintering; cold pressing and sintering thulium oxide wafers; preparation of thulium and/or ytterbium oxide powder via precipitation with oxalic acid, ammonium oxalate, urea and methyl oxalate; determination of the total… more
Date: June 1, 1970
Creator: Nelson, C.A.; Anderson, R.W.; Talbot, M. & Bierds, W.
Partner: UNT Libraries Government Documents Department
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