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Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies

Description: Report regarding the calcination of full level Purex and Redox waste carried out "in a remotely operated pilot plant consisting of a radiant-heat spray calciner and a pot calciner and their associated off-gas equipment" (p. 4). This contains details of the calcination, effects on the waste, and difficulties encountered.
Date: September 1964
Creator: Allemann, R. T.; Roberts, F. P. & Upson, U. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments

Description: Report issued by the Argonne National Laboratory discussing a computer program used for fast reactor safety experiments. As stated in the summary, "this report gives a detailed description of a hybrid-computer program for calculating temperatures in a multi-region, axisymmetric, cylindrical configuration consisting of solid materials bounded by flowing coolant. Included is an explanation of the mathematical methods, together with a discussion of special features, input-output descriptions, and … more
Date: September 1967
Creator: Bryant, Lawrence T.; Amiot, Lawrence W.; Dickerman, Charles E. & Stephany, William P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal Conductivity of UO2

Description: Report discussing the thermal conductivity of uranium dioxide. The first part of the report includes the thermal effects on the substance's physical form, while the second part describes the experimental details.
Date: September 1962
Creator: Daniel, J. L.; Matolich, J., Jr. & Deem, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pressure and Thermal Stresses at a Pipe Attachment to a Sphere

Description: Abstract: Design nomographs and equations have been prepared for determining the bending stresses and hoop stresses at the junction of a cylinder and sphere when: (1) Internal pressure exists in the sphere and (2) There is a difference in average temperature between the cylinder and the sphere. A correlation of calculated stresses and photoelastically determined stresses for models with internal pressure is presented.
Date: September 21, 1959
Creator: Deagle, Lorenzo
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Energy Transfer Between Modified Maxwell Distributions

Description: Abstract: "A particularly conventional modified form of Maxwell distribution is chosen. The modified expressions for (a) the energy transfer from the ions to the electrons in a plasma and (b) the brehmestrahlung from the electrons are calculated. Using the expressions some possible steady-state conditions for the ion and electron gases are derived and compared with those for the usual Maxwell distributions."
Date: September 20, 1956
Creator: Greyber, Howard D. & Bing, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High Temperature Corrosion of Some Metals and Ceramics in Fluorinating Atmospheres

Description: Abstract: The results of this investigation leave little doubt that diffusion of the fluorinating gas along the grain boundaries of the nickel fluoride film to react at the metal-scale interface is the primary mechanism of attack upon pure nickel and its more promising alloys.
Date: September 30, 1960
Creator: Hale, C. F.; Barber, E. J.; Bernhardt, H. A. & Rapp, Karl E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

Description: Report documenting "the long-term irradiation stability of the graphite used as the moderator in the Experimental Gas Cooled Reactor (EGCR) at Oak Ridge" (p. 1) by irradiating capsules at the General Electric Test Reactor. This includes the design and construction of the experiment, experiment procedures, and results of irradiation. Appendices begin on page 83.
Date: September 1964
Creator: Helm, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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OMR Control-Safety Rod Component Development Tests

Description: Abstract: A magnetic-jack control-safety rod is under development for the 45.5 thermal megawatt Organic Moderated Reactor. The rod is "unitized," i.e., the poison element, drive, position indicator, and shock absorber are contained in a compact assembly which is inserted in a regular fuel channel opening in the core. Tests to develop components capable of operating under these conditions are described and results are reported.
Date: September 15, 1959
Creator: Howell, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Two-Phase Pressure Losses Quarterly Progress Report: Sixth Quarter, May 12, 1963 - August 12, 1963

Description: Technical report describing that the pressure drops along 3/4-inch, 1-inch, and 1-1/4 inch straight pipes and across three contraction-expansion inserts in a 1-inch pipe have been measured under both single- and two-phase flow conditions. Pressure was varied from 600 to 1400 psia, flow from 0.25 x 10(6) to 1.66 x 10(6) lb/hr ft, and quality from zero to 90 percent. The single-phase pipe friction factor agrees with the Moody value for smooth pipe. The two-phase friction for horizontal flow shows… more
Date: September 1, 1963
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Description: Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.
Date: September 1961
Creator: Kosut, B. S.; Leggett, R. D. & Marshall, R. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant

Description: From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
Date: September 30, 1959
Creator: Linenberger, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Adiabatic Injection

Description: From introduction comments: The present analysis is intended to examine the relations for "adiabatic" injection in general from a different point of view.
Date: September 22, 1955
Creator: Linlor, William I., 1915-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Continuous injection processing

Description: From introduction: "In this report we consider a few non-adiabatic processes. The types to be discussed will be limited because of two reasons: first, complete descriptions are available for some processes; second, as time goes on alternative injection methods undoubtedly will be discovered, so this list must necessarily be incomplete."
Date: September 23, 1955
Creator: Linlor, William I., 1915-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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