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Analysis of the Heat Generation in the Primary Sodium Pipe Tunnels, Intermediate Heat Exchanger Cells, and the Primary Sodium Fill Tank Vault for the Hallam Nuclear Power Facility (Hnpf)

Description: I. An adequate and conservative calculational method for evaluation of the heat generation distribution in the primary sodium system substructural areas was developed. The method was programed for the IBM 704 and the IBM 709. The results obtained from analysis of the gamma heat generation in the primary sodium pipe tunnels and in the intermediate heat exchanger cells are presented. Calculations are outlined, and gamma attenuation coefficients for concrete, sodium, and steel are given. II. Resul… more
Date: March 27, 1959
Creator: Legendre, P. J.
Item Type: Refine your search to only Report
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BOUNDARY CONDITIONS AND CONSERVATION PROPERTIES OF FOPP, A PLASMA FOKKER- PLANCK CODE

Description: The energy distribution of ions and electrons in DCX are being studied by means of the Fokker-Planck approximation to the Boltzmann equation. An IBM- 704 code, called FOPP, was constructed to solve simultaneously the coupled Fokker-Planck equations for each of the two species of particles. This report discusses the difference scheme employed and derives the boundary conditions necessary in order that this difference scheme conserve energy and particles in the absence of sources and sinks. In pa… more
Date: February 27, 1959
Creator: Fowler, T.K.; Rankin, F.M. & Simon, A.
Item Type: Refine your search to only Report
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Design criteria -- Modification of fuel element test facilities. 1706-KER Project CGI-839

Description: The following criteria outlines the basis, objectives, and fundamental methods that shall govern the preparation of final design for ``Project CGI-839, Modification to Fuel Element Test Facilities -- 1706 KER.`` These modifications will provide the equipment to test NPR size fuel elements in the KER recirculating loops. The 1706-KER Recirculation Test Facility of KE Reactor is operated to obtain experimental data regarding high temperature reactor coolant technology and high temperature fuel el… more
Date: August 27, 1959
Creator: Rudock, E. R.
Item Type: Refine your search to only Report
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DIFFUSION OF PLASMA PARTICLES ACROSS A MAGNETIC FIELD

Description: BS>A previous calculation of the rate of diffusion of like charged particles across a magnetic field is generalized. No "a priori" assumption as to the relative magnitude of certain terms need be made and spatial density gradients are permitted in both directions perpendicular to the field. The final result agrees with that given earlier. (auth)
Date: November 27, 1959
Creator: Isihara, A. & Simon, A.
Item Type: Refine your search to only Report
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The Economics of Nuclear Power

Description: Economic aspects of nuclear power development in the U. S. are tabulated and graphed. Included are figures on presently operating reactors as well as those contemplated or scheduled. Also a brief description of the objectives of short- and long-range programs is given as well as tables listing some of the characteristics of each reactor. (J.R.D.)
Date: April 27, 1959
Creator: Lane, J.A.
Item Type: Refine your search to only Report
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THE EFFECT OF IMPURITIES ON IRON-CHROMIUM-YTTRIUM ALLOYS

Description: A study was made of the effect of carbon, manganese, oxygen, palladium, and sulfur on the structure and fabricability of iron-35 wt.% chronium-1 wt.% yttrium alloy. Using a vacuum-induction melting technique each of the additives except oxygen was introduced to 1-lb remelts of a single 15-lb master alloy. The master alloy and remelts were made under similar melting, pouring, and casting conditions. Oxygen was introduced as Fe/sub 2/0/sub 2/ by inertelectrode arc melting to avoid extraneous, unc… more
Date: April 27, 1959
Creator: Endebrock, Row W.; Chubb, Walston; Foster, Ellis L. & Dickerson, Ronald F.
Item Type: Refine your search to only Report
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Effect of saturation of water with dissolved corrosion product on the in-reactor corrosion rate of aluminum in deionized water: Proposal for test in 1706 KER

Description: This report discusses a proposal to measure the corrosion rate of aluminum-clad DOE elements in deionized water in one of the KER Loops at the highest obtainable surface temperatures under conditions where the bulk water adjacent to the elements is saturated with aluminum corrosion product. This will determine whether in-reactor corrosion may be reduced by controlling the aluminum concentration in the water and also provide corrosion data in deionized water at higher temperatures than is now av… more
Date: January 27, 1959
Creator: Dickinson, D. R.
Item Type: Refine your search to only Report
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EFFECTS OF TERNARY ADDITIONS OF ALUMINUM-35 w/o URANIUM ALLOYS

Description: The effects of a number of ternary additions on the constitution, casting, and fabricating characteristics and the physical properties of aluminum- 35 wt.% uranium were investigated. Initial investigations were concerned with the effects of 3 at.% ternary additions on the microstructure and press-forging characteristics of the alloy. It was found that additions of this magnitude often introduced extrinsic phases in the alloy. At the 3 wt% level, additions of germanium, silicon, tin, or zirconiu… more
Date: October 27, 1959
Creator: Daniel, Norman E.; Foster, Ellis L. & Dickerson, Ronald F.
Item Type: Refine your search to only Report
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Effects of Ternary Additions on Aluminum-35 w/o Uranium Alloys

Description: Abstract: "The effects of a number of ternary additions on the constitution, casting, and fabricating characteristics and the physical properties of aluminum-35 w/o uranium were investigated. Initial investigations were concerned with the effects of 3 w/o ternary additions on the microstructure and press-forging characteristics of the alloy. It was found that additions of this magnitude often introduced extrinsic phases in the alloy. At the 3 w/o level, additions of germanium, silicon, tin or z… more
Date: October 27, 1959
Creator: Daniel, Norman E.; Foster, Ellis L. & Dickerson, Ronald F.
Item Type: Refine your search to only Report
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ELECTROLYTIC DISINTEGRATION OF ZIRCALOY-2 IN NITRIC ACID SOLUTIONS

Description: Zircaloy-2 is anodically converted to scaly ZrO/sub 2/ at 60 deg C in 8 M HNO/sub 3/. About 0.5 mole of acid is consumed per faraday, and after saturation of the electrolyte with nitrogen oxides about 0.3 mole of gas is evolved per faraday. The nitric acid is reduced to hydrogen, NO, and N0/sub 2/, with hydrogen predominating if the cathode is Zircaloy and NO if the cathode is platinum. Corrosion specimens of HRT metals were exposed to the electrolysis conditions. From determinations of the dec… more
Date: November 27, 1959
Creator: Clark, W. E. & Peterson, S.
Item Type: Refine your search to only Report
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Fast Neutron Flux Measurements for Shielding Applications

Description: Pressed sulfur pellets, irradiated for two hours at 10 w yielded satisfactory counting rates on an internal proportional counter for measuring fast neutrons. The pellets were counted in their original form and an equation applicable to thick sources was applied to obtain disintegration rates. Decay data and beta energy analyses indicated that the induced activity was due to P/ sup 32/. Cross section values reported in the literature for the S/sup 32/(n,p)P/ sup 32/ reaction involved were found … more
Date: August 27, 1959
Creator: Roy, M.
Item Type: Refine your search to only Report
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FLOODING CHARACTERISTICS OF 1/4-in. FLUOROTHENE RASCHIG RINGS

Description: The flooding characteristics of fluorothene Raschig rings at low liquid rates with the existing literature data on carbon rings are compared. Visual observations of flooding in the air-water system were correlated with pressure drop using a 3-in. i.d. glass column having an 18-in. long fluorothene Raschig ring packed section. A comparison of extrapolated literature data with these experimental data indicates thc gas flow rates required to flood fluorothene packing are slightly higher than for c… more
Date: April 27, 1959
Creator: Boles, R. L. & Stainker, S. H.
Item Type: Refine your search to only Report
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Fuel Cycle Costs in a Graphite Moderated U$sup 235$-Th Fueled Fused Salt Reactor

Description: A fuel-cycle economic study was made for a 315-Mw(e) graphite-moderated U/sup 235/-Th-fueled fused-salt reactor. Fuel cycle costs of approximately 1.3 mills/kwh may be possible for such reactors when reprocessed for U/sup 233/ and U/ sup 235/ recover y at the end of a 9-year cycle. Continuous removal of fission products during the reactor cycle does not appear to offer any great economic advantage for the converter reactor considered. (auth)
Date: February 27, 1959
Creator: Guthrie, C. E.
Item Type: Refine your search to only Report
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Further Studies of Sintered Refractory Uranium Compounds

Description: The refractory uranium compounds UC and UC/sub 2/ were prepared by arc- melting methods, UN by gas solid reactions, and UB/sub 2/ and UBe/aub 13/ by solid-solid reactions. Techniques for sintering powder compacts of these compounds to densities 90% of theoretical or greater were developed. Mean linear thermal-expansion coefficients of 7.9 x 10/sup -6/ per deg F for Uc and 9.3 x 1O/ sup -6/ per deg F for UBe/sub 13/ were obtained in the range 68 to 1800 deg F. The thermal conductivity of sintere… more
Date: January 27, 1959
Creator: Tripler, A. B., Jr.; Snyder, M. J. & Duckworth, W. H.
Item Type: Refine your search to only Report
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Heat Transfer Study for Self-Boiling Radioactive Wastes

Description: The temperature characteristics associated with the handling of self-boiling radioactive wastes from the separations extraction processes in the Chemical Processing Department have necessitated several heat transfer studies. Earlier studies 1,2,3 defined the feasibility of self-concentration in existing waste storage facilities by determining the rate of heat generation from the decay of stored fission products and by defining the rate of heat loss from existing storage tanks to the surrounding… more
Date: April 27, 1959
Creator: Stivers, H.W. & Taylor, H.W.
Item Type: Refine your search to only Report
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LABORATORY DEVELOPMENT OF A PROCESS FOR SEPARATING BARIUM-140 FROM MTR FUEL

Description: S>The results of all laboratory research and development on the process for separation of barium-140 from MTR fuel elements are presented. The steps include caustic dissolution separation of barium and strontium with fuming nitric acid and removal of strontium by the chromate-acetate method. The results of laboratory and pilot plant corrosion investigations and high radiation level flowsheet tests in the Multicurie Cell are also included. ( auth)
Date: March 27, 1959
Creator: Anderson, E. L.; MacCormack, R. S. & Slansky, C. M.
Item Type: Refine your search to only Report
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Linear Accelerator for Heavy Ions

Description: The following report discusses the construction of two heavy-ion linear accelerators, one at the the University of California Radiation Laboratory and the other at Yale University. The goal for these accelerators is to produce ions of masses up to that of neon with energies of 10 Mev per nucleon.
Date: March 27, 1959
Creator: Wells, Don
Item Type: Refine your search to only Report
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MICRO-ELECTROPHORETIC DETERMINATION OF THE ZETA POTENTIAL OF THORIUM OXIDE

Description: A micro-electrephoresis cell is described, and its application to the determination of the zeta potential of thorium oxide is presented. Samples of thorium oxide from different sources, some of which were subjected to certain physical treatments, are charcterized by the zeta potential obtained in water. The zeta potentials produced in solutions of HCl, H/sub 2/SO/sub 4/, KOH, NaOH, Na/sub 4/P/sub 2/O/sub 7/ and Na /sub 3/PO/sub 4/ are also given
Date: November 27, 1959
Creator: Boyd, C. M.; House, H. P. & Menis, O.
Item Type: Refine your search to only Report
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ML-1-1A CORE STUDIES WITH THE GCRE CRITICAL ASSEMBLY

Description: Critical assembly studies were conducted tc provide physics and engineering data to aid in developing the Mobile Low-Power Reactor (ML-1). The ML-1-lA core was critical with 59 elements containing 17,906.71 g of U/sup 235/ and had an excess reactivity of 0.381 x 10/sup -2/ DELTA k/k at a moderator temperature of 24.91 deg C. The ratio of maximum element power to core-averaged power was approximately 1.09. The ratio of maximum to core-averaged thermal flux was approximately 1.10. At an 18-deg se… more
Date: November 27, 1959
Creator: Egen, Richard A.; Hogan, William S.; Dingee, David A. & Chastain, Joel W.
Item Type: Refine your search to only Report
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Multiplication Measurements With Highly Enriched Uranium Metal Slabs

Description: A series of neutron multiplication measurements with arrays of 1 by 8 by 10 in. slabs of 93.4% U/sup 235/-enriched uranium metal was made to provide data from which safety criteria for the storage of these fissile units can be established. Each slab contained 22.9 kg of U/sup 235/. A maximum of 125 units was assembled. The arrays studied were cubic lattices of the units and were usually parallelepipedal in shape. Arrays were both unmoderated and Plexiglas- moderated and were surrounded in most … more
Date: July 27, 1959
Creator: Mihalczo, J. T. & Lynn, J. J.
Item Type: Refine your search to only Report
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Multiplication Measurements with Highly Enriched Uranium Metal Slabs

Description: A series of neutron multiplication measurements with arrays of 1 by 8 by 10 in. slabs of 93.4% U235-enirched uranium metal have been made to provide data from which safety criteria for the storage of these fissile units can be established. Each slab contained 22.9 kg of U235. A maximum of 125 unites was assembled. The arrays studied were cubic lattices of the units and were usually parallelepipedal in shape.
Date: July 27, 1959
Creator: Mihalczo, J. T. & Lynn, J. J.
Item Type: Refine your search to only Report
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Niobium Phase Diagrams : Manuscript Report on Niobium-Oxygen System

Description: Abstract: "The niobium-oxygen equilibrium has been determined by metallographic examination of arc-cast alloys made of electron-gun-refined niobium metal and special purity niobium pentoxide. Two intermediate oxides, NbO and NbO2, melt without decomposition at 1945 C and 1915 C, respectively. Eutectic reactions exist between niobium and NbO and 1915 C and between NbO and NbO2 at 1810 C. Experimental supports a peritectic reaction between NbO2 and Nb2O5 1510 C. The maximum solid solubility of ox… more
Date: April 27, 1959
Creator: Elliott, Rodney P.
Item Type: Refine your search to only Report
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