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Technical basis for establishing process tube pressure limits for KER loops 2 and 3 and for the NPR Prototype Facility

Description: In compliance with a request from Coolant Testing Operation, the Reactor Engineering Operation has made a study to determine the maximum operating pressure limits for the pertinent Zircaloy-2 process tubes. Since these tubes shall be used for testing NPR fuel elements, it is considered desirable that KER Loops 2 and 3 permit operation at temperatures of around 300{degrees}C while the NPR prototype facility permit operation at about 316{degrees}C in a manner such that there is minimum hazard to … more
Date: June 26, 1959
Creator: Adams, O. E.
Partner: UNT Libraries Government Documents Department
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Production test IP-245-A dual area trip-out of B & C Reactor process pumps

Description: The objectives of the test described in this report are to obtain current knowledge of the flow characteristics of the B and C Reactor flow systems under various transient conditions that have a reasonable probability of occurrence. These tests will be used to revaluate the B and C Reactor bulk temperature limits, the Ball 3X low pressure trip settings, and quantitative adequacy of emergency flow from the combined high tanks - export system.
Date: March 26, 1959
Creator: Long, J. T. & Jones, S. S.
Partner: UNT Libraries Government Documents Department
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Irradiation performance of coextruded enriched uranium fuel rod PT-IP-A172-A: Final report

Description: The proposed operating conditions for fuel elements to be charged into the NPR require the fuel to be of an extended surface geometry and maintain adequate strength and corrosion resistance in 300 C water. A contract was let to Nuclear Metals Inc. to produce by co-extrusion lengths of fuel rod containing both natural and 1.6% enriched uranium of irradiation quality for fabrication into fuel elements. The fuel rods used in the irradiation test represent the first enriched uranium rods coextruded… more
Date: May 26, 1959
Creator: Claudson, T. T.
Partner: UNT Libraries Government Documents Department
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Sizes of U. S. Steam-Electric Plants

Description: At the present time, plants in the 100 to 500 Mw size range are more numerous and carry the greatest portion (over 50%) of the total steam-electric plant load in the US utillties industry. The contribution of plants of over 1,000-Mw capacity is increasing more rapidly than any other size classification and at present represents about 10% of the total capacity. By 1962 the TVA will have six plants with capacities of over 1,000-Mw. The largest steam-electric plant in the US is the TVA plant at Ki… more
Date: May 26, 1959
Creator: Robertson, R. C.
Partner: UNT Libraries Government Documents Department
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FOREIGN RESEARCH AND POWER REACTOR PRELIMINARY LIST

Description: Foreign research and power reactors are tabulated. Nuclear power buildup goals are given for each nation on which information is available. (J.H.D.)
Date: February 26, 1959
Creator: Ullmann, J.W.
Partner: UNT Libraries Government Documents Department
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Eurochemic Assistance Program: Comments by ICPP, Dated March 17, 1959, on Questions for Eurochemic

Description: Comments by ICPP personnel on questions posed by Eurochemic Company are presented. Included is information on a fumeless dissolution system, recycle and rework system, liquid waste storage, criticality. in-line instrumentation, and a report listing Idaho Operations Area costs. (J.R.D.)
Date: March 26, 1959
Creator: Weech, M. E.
Partner: UNT Libraries Government Documents Department
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Critical Assemblies of Uranium Metal

Description: Data on critical assemblies of fissionable uranium metals are summarized. Empirical studies are made for spccific reflectors and gcometrics to determine the fcasibility of extrapolating these data for conditions concerning nuclcear safcty problems. Also included are the influencs on critical systems by various reficctors, U-235 isotopic enrichment, density, and small metal pieces homogcncously distributed in water. (auth)
Date: March 26, 1959
Creator: Gwin, R. & Mee, W. T.
Partner: UNT Libraries Government Documents Department
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A TECHNIQUE FOR PREPARING NEPTUNIUM TARGETS OF UNIFORM CROSS SECTION

Description: As a result of a request for targets of uniform cross section for determination of the fission cross section of neptunium, an evaporation technique was developed for preparing films of the desired uniformity. Despite the fact that neptunium is an alpha emitter, it was possibIe to contain the activity and to subsequently recover the neptunium. (auth)
Date: March 26, 1959
Creator: Massey, B.J.
Partner: UNT Libraries Government Documents Department
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X-RAY DIFFRACTION ANALYSIS OF BORON IN BORON CARBIDE

Description: By applying the relationships between lattice parameters and composition in the solid solution range, a method was presented to analyze boron in boron carbide. The purpose was to establish a means of determining the boron composition in a boron carbide solid solution in the presence of excess carbon or boron. The different unit-cell dimensions sometimes reported for a given solid mixture are usually attributed to the existence of solid solutions. If the crystal lattice parameters vary linearly … more
Date: May 26, 1959
Creator: Osika, L.M.
Partner: UNT Libraries Government Documents Department
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THE DEVELOPMENT OF A FLUIDIZED BED REACTOR FOR THE FLUOROX PROCESS: UNIT OPERATIONS MONTHLY STATUS REPORTS FOR THE PERIOD NOVEMBER 1958 THROUGH MAY 1959

Description: Results of four experimentul runs in the Fluorox fluidized bed reactor system are reported. The engineering feasibility of UF/sub 6/ production from UF/ sub 4/ by use of dry air of O/sub 2/, 2UF/sub 4/ + O/sub 2/ = UF/sub 6/+ UO/sub 2/ F/sub 2/, in an Inconel fluidized bed reactor at 800 to 850 deg C was demonstrated in two experimental tests in which greater than 90% of the theoretical amount of UF/sub 6/ was collected or measured. Two runs made with crude UF/sub 4/ (produced from unpurified m… more
Date: May 26, 1959
Creator: Bresee, J C; Horton, R W & Scott, C D
Partner: UNT Libraries Government Documents Department
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NATURE OF RADIOACTIVE WASTES

Description: The integrated processes of nuclear industry are considered to define the nature of wastes. Processes for recovery and preparation of U and Th fuels produce wastes containing concentrated radioactive materials which present problems of confinement and dispersal. Fundamentals of waste treatment are considered from the standpoint of processes in which radioactive materials become a factor such as naturally occurring feed materials, fission products, and elements produced by parasitic neutron capt… more
Date: January 26, 1959
Creator: Culler, F.L. Jr.
Partner: UNT Libraries Government Documents Department
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THERMAL STRESS ANALYSIS OF CYLINDRICAL SHELLS

Description: BS>Part I of this report describes the analysis of a cylindrical shell subjected to a temperature variation in the axial direction. This part is divided into two sections. Section 1 gives the formulas and the procedure for their application. ln Section 2, the derivations of the cylindrical shell formulas are given. A cylindrical shell subjected to a linear temperature variation through the thickness is considered in Part II. Part III cortains some sample problems which require the metheds of Pa… more
Date: March 26, 1959
Creator: Witt, F.J.
Partner: UNT Libraries Government Documents Department
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ANSWERS TO QUESTIONS ON OFF-GAS TREATMENT. Eurochemic Assistance Program: Comments by HAPO, dated March 12, 1959, on Questions by E.L. Nicholson

Description: Information relative to the performance and operation of silver reactors is presented. The information is given as answers to questions submitted in the USAECEurochemic Company cooperative program. The answers to 8 questions are presented along with the basis for comments. (J.R.D.)
Date: March 26, 1959
Creator: Bupp, L. P.
Partner: UNT Libraries Government Documents Department
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FATIGUE STUDIES OF INCONEL

Description: No Description Available.
Date: June 26, 1959
Creator: Carlson, R.G.
Partner: UNT Libraries Government Documents Department
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THE CRITICAL CURRENT IN THE CASE OF NEUTRAL AND PLASMA BREAKUP

Description: An estimate of the critical current for the case of breakup by an arc has been obtained. It is shown that the same technique allows a quick estimate of the critical current in the case of no arc, using neutral and plasma breakup instead. (auth)
Date: February 26, 1959
Creator: Simon, A.
Partner: UNT Libraries Government Documents Department
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Reprocessing of Are Fuel, Volatility Pilot Plant Runs E-3 Through E-6

Description: Reprocessing of the ARE fuel was resumed after extensive leak testing in the pilot plant. This was considered necessary to assure no recurrence of gaseous UF/sub 6/ leaks as experienced in Run E-2. In the four additional runs required to complete the program, about 641 kg of fluoride salt containing 40.64 kg of fully enriched uranium was reprocessed. Recovery as UF/sub 6/ product represented 97.97% of the feed, with 0.01% measured losses. An additional 2.14% was reclaimed from NaF beds. The pro… more
Date: August 26, 1959
Creator: Whitmarsh, C. L.
Partner: UNT Libraries Government Documents Department
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NUCLEAR EXCURSION ANALYSIS ON THE IBM 650 (EARLY CODE)

Description: The Early Program is designed to compute the peak power and total energy release vhich will occur in a reactor due to a step increase of reactivity. These excursions may be terminated by one of several automatic shutoff mechanisms caused by the power excursion itself. The calculation assumes no thermodynanaic delays and assumes void formation is due to heat conduction from the cladding to the moderator. (W.D.M.)
Date: February 26, 1959
Creator: Reiback, E.M. & Stueck, C.J.
Partner: UNT Libraries Government Documents Department
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NUCLEAR EXCURSION ANALYSIS ON THE IBM 650 (EARLY CODE)

Description: The early program is designed to compute the peak power and total energy release which will occur in a reactor due to a step increase of reactivity. The calculation assumes no thermodynamic delays and assumes void formation is due to heat conduction from the cladding to the moderator. For periods in the 1 to 10 msec. range, the calculation yields results which are in excellent agreement with SPERT experimental results. (W.D.M.)
Date: February 26, 1959
Creator: Stueck, C.J. & Reiback, E.M.
Partner: UNT Libraries Government Documents Department
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Preliminary hazards review operational charge-discharge for Hanford reactors

Description: The use of the porposed full reactor operational charge-discharge facilities will to some degree change the method of reactor operation from a ``batch`` to a ``continuous`` process. This change in the operational process will require modifications to coolant flow supply and monitoring equipment. Since a continuous and adequate coolant supply is essential to prevention of the release of fission products from the irradiated fuel elements this modification merits a hazards analysis.
Date: October 26, 1959
Creator: Carlson, P. A. & Trumble, R. E.
Partner: UNT Libraries Government Documents Department
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Reflector and Pressure Vessel Cooling and Thermal Stress Analysis on the IBM 650

Description: S>These programs are intended to:ssist in establishing reflector cooling requirements, as well as thermal stresses in the reflectors and pressure vessel. The main program (304-Rec I) establishes required velocities between reflectors as a function of geometry, heat generation rates, material and fluid properties, and allowable surface temperature. This is done by iterating on velocities for successive water gaps. When required velocities have been established, corresponding thermal stresses are… more
Date: March 26, 1959
Creator: Love, J.D. & Caton, R.L.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report for March 1959

Description: In a preliminary experiment, the integral diffusivity of 1 M FeCl/sub 3/ solution varied uniformly with the fraction difiused: from 0.3 x 10/sup -6/ cm/ sup 2//sec for 10 per cent diffused to 0.8 x 10/sup -6/ for 30 per cent diffused. A short Fluorox run made with crude UF/sub 4/ in the 4-in. fluidized bed showed that UF/sub 6/ could be produced from the impure feed. Denitration of Th(NO/sub 3/)/sub 4/ solutions on fluidized or mechanically agitated beds of ThO/sub 2/ and gave fine ThO/sub 2/ p… more
Date: June 26, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Partner: UNT Libraries Government Documents Department
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