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1706 KE Water Treatment for Out-of-Reactor Test Facilities.

Description: Water treatment systems for preparing and maintaining high purity water in out-of-reactor or in-reactor test oops are becoming increasingly important. In out0of-reactor experiments the presence of ionic impurities in the water has a marked influence on film formation and corrosion rates. It is therefore , imperative that these impurities be maintained at the lower practical concentration.
Date: March 30, 1959
Creator: Demmitt, Thomas F.
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AIR CORE CRYOGENIC MAGNET COILS FOR FUSION RESEARCH AND HIGH ENERGY NUCLEAR PHYSICIS APPLICATIONS

Description: It is shown that cryogenic techniques offer the possibility of substantially improving the efficiency and practicality of generating high magnetic fields in air-core coils of large size. Over-all reductions in power requirements of as high as 25, by comparison with conventional coils, are predicted, provided high purity conductors and efficient refrigeration cycles are used. (W.D.M.)
Date: October 30, 1959
Creator: Post, R. F. & Taylor, C. E.
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Chemical Technology Division, Unit Operations Section Monthly Progress Report for January 1959

Description: Two alternate systems, acetic acid-nickel and acetic acid-cobalt, were examined for possible replacement of the corrosion system: ferric chloride-nickel which is being used in the current transpiration corrosion protection studies. Two Fluorox fluidized bed runs were made, of 9 and 58 hr duration, in which dry air and oxygen were used as oxidizing and fluidizing gases. Tests of the hydroclone classification of thoria indicated that more than 95% of the +0.5 micron particles can be removed from … more
Date: April 30, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
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Corrosion of INOR-8 and Inconel Dissolver Components of the Fluoride-Volatility Process

Description: The corrosion of INOR-8 and Inconel dissolver components used in the fluoride volatility process for the dissolution of zirconium with anhydrous HF in molten salts was investigated. Ten dissolution runs were made using simulated subassemblies formed from Zircoloy-2. The dissolver and components were made from INOR-8. Both the dissolver vessel and draft tube were examined several times during the series of runs. The solids which formed at different areas in the system were also analyzed. The res… more
Date: December 30, 1959
Creator: Fink, Frederick W.
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CUREBO: A GENERALIZED TWO-SPACE-DIMENSIONAL CODING WITH CROSS-SECTION AND DEPLETION CALCULATIONS FOR THE IBM 704

Description: The CUREBO code for the IBM 704 is described. The code is divided into three parts including the calculation of nuclear cross section of the various physical components of a reactor (WOX7), the solution of the multigroup diffusion equations in two-space dimensions in order to find neutron fluxes and sources for an operating reactor containing these components ( CURE), and the calculation of fuel and poison depletion as a result of operating this reactor under steady- state conditions (BO2). (au… more
Date: April 30, 1959
Creator: Archibald, J.A. Jr.
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Description of Purex Plant Process

Description: A brief summary, with reference literature for details, of pertinent and important process flowsheet conditions which are in use in the Purex Process is presented. (auth)
Date: April 30, 1959
Creator: Irish, E. R.
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The Design of Large Cryogenic Magnet Coils : Paper No. 2

Description: Abstract: "Preliminary design and experimental work aimed toward fabrication of large magnet coils with encapsulated sodium conductors is outlined. Aspects of cooling cycles are discussed along with heat transfer, thermal stability, and the mechanical reinforcement of such coils."
Date: October 30, 1959
Creator: Post, Richard F. & Taylor, C. E.
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The Design of Large Cryogenic Magnet Coils. Paper No. 2

Description: Preliminary design and experimental work aimed toward fabrication of large magnet coils with encapsulated sodium conductors is outlined. Aspects of cooling cycles are discussed along with heat transfer, thermal stability, and the mechanical reinforcement of such coils. (J.R.D.)
Date: October 30, 1959
Creator: Taylor, C. E. & Post, R. F.
open access

Determination of Flux Levels in Neutron Detector Wells. Section II. First Performance. Core I, Seed 1. Test Results DL-S-242, T-641311

Description: The purpose of the test was to determine the neutron flux level in a BF3 counter well during the second performance of DL-S-225. The measured activity of the irradiation brass bolt was due entirely to the radioactive decay of Zn65. The thermal neutron flux in the BF3 counter well during the second 1000 hour run was calculated to be 2.5 x 10(9) neutrons/cm2 sec.
Date: October 30, 1959
Creator: George, John R. & Cappola, M., Jr.
open access

DETERMINATION OF MAXIMUM PERMISSIBLE LEAKAGE FROM THE HRT PROCESS STEAM SYSTEM

Description: Calculations were made to determine the radiation hazard to HRT personnel as a result of leakage to the atmosphere from the process steam system in the event of a heat exchanger tube rupture. These calculations show that with the present four-minute delay before dumping approximately 1020 lb of fuel solution may be transferred to the steam system. The radiation hazard from fission products in the atomosphere will be negligble if the steam killer blower is operating. If this blower is not operat… more
Date: January 30, 1959
Creator: Gift, E.H.
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Dissolution of Zirconium Matrix Fuels in Molten Fluoride Salts

Description: The application of the Volatility Process for reprocessing spent reactor fuels to zirconium fuel elements requires the conversion of the fuel to a fluoride form. This conversion can be accomplished by the dissolution of such fuels in a bath of molten fluoride salts with a hydrogen fluoride sparge. Studies with dummy zirconium fuel elements showed dissolution rates averaging 2 mg/sq cm-min. The effect of submergence, geometrical configuration, and HF impingement rate appeared more significant th… more
Date: January 30, 1959
Creator: Horton, R. W. & Whatley, M. E.
open access

Electrophoretic Processes--Nuclear Aspects. Final Report for December 1, 1956-June 30, 1959. Vitro Job 2091

Description: The feasibility of the electrophoretic (electrokinetic) coating process has been demonstrated for a number of nuclear applications. The major portion of the experimental program was directed toward work which leads to: development of electrophoretic coatings which should be useful for the protection of graphite and graphite fuel elements against physical and chemical attack under reactor conditions. Several of these coatings also show promise for fission product retention; a technique for apply… more
Date: September 30, 1959
Creator: Keeler, R. A. & Klach, S. J.
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Equations of State for Stream-Water Mixtures and Some Representative Applications Analysis

Description: The majority of two-phase flow problems involving equations of state are solved by use of point-wise utilization steam table values. In this manner, problems involving the use of the various flow equations of continuity, momentum and energy are generally forced into iterative solutions. Considerable effort towards the development of an analytical expression for the state equation seems indicated so as to simplify the analysis of two-phase problems, particularly apparent in the analysis of syste… more
Date: November 30, 1959
Creator: Love, W. J.
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AN ESTIMATION OF THE EXPLOSION HAZARD DURING REPROCESSING OF METALLIC URANIUM FUEL ELEMENTS METALLURGICALLY BONDED TO ZIRCALOY CLADDING

Description: BS>Experimental studies were performed to define the behavior in ammonium fluoride solutions of uraniumzirconium alloys and of explosive residues isolated from such alloys. The results indicate that once the diffusion layer existing between the uranium core and the Zircaloy cladrung is exposed to such solutions, it will readily and completely dissolve, thus eliminating the possibility of this portion of the diffusion layer entering into an explosive reaction with nitric acid. Because of the pro… more
Date: September 30, 1959
Creator: Swanson, J.L.
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An Estimation of the Explosion Hazard During Reprocessing of Metallic Uranium Fuel Elements Metallurgically Bonded to Zircaloy Cladding

Description: Through the years, considerable effort has been expended in studies of the explosive reactions sometimes observed in the dissolution of uranium-zirconium alloys in nitric acid. It has been shown (1) that such reactions result from the rapid oxidation of finely dived solids released by the preferential dissolution of the metallic matrix. The explosive portion of such solids has been identifies (1) as an intermetallic compound with the approximate composition UZr2. This compound, referred to as t… more
Date: September 30, 1959
Creator: Sanson, J. L.
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Final Report, Design Test PR-20 Calandria Characteristics

Description: Design Test Request PR-20 Calandria Characteristics, outlined the need for experimental data concerning the performance of the calandria under transient conditions. Test data was required to confirm that the moderator dump system would drop the level the required 24 inches in less than one second. The original calandria dump chamber design was modified until the criteria was met. This information is recorded in HW-58333, Interim Report, Design Test PR-20, Calandria Characteristics, which lists … more
Date: October 30, 1959
Creator: Gruver, R. L.
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Final Technical Report on Physics Research

Description: Results are summarized on theoretical considerations of the excited states of the Ca isotopes, experimental studies of the level structure of Ca42 and Ca44, studies of the production of circularly polarized bremsstrahlung by beta rays, the Moller scattering spectrometer, and the Moller scattering coincidence experiment.
Date: November 30, 1959
Creator: McCullen, J. D.; Kraushaar, J. J.; Woolum, J. C.; Sandifer, C. W.; Kliwer, J. K.; Baker, D. et al.
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FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. PHASE I. Progress Report for May 1, 1959 to October 31, 1959

Description: Numerous types of high temperature ceramic fuel elements for the Pebble Bed Reactor are being evaluated. Specimens are 1 1/2 in. diameter uranium graphite spheres with external coatings such as silicon carbide or pyrolytically deposited high density graphite and fuel particle coatings such as alumina. Low fission product leakage rates at high temperatures have been observed for some of these coatings. High-level irradiation has given no visible evidence of radiation damage to either the silicon… more
Date: November 30, 1959
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FUNDAMENTALS OF DIFFUSIONAL BONDING--IV. Fourth Annual Progress Report for July 1, 1958 through June 30, 1959

Description: Investigatlon of interdiffusion in the aluminumuranium system and of the effects of applied pressure on such systems was about completed. The growth kinetics of the UAl/sub 3/ phase were determined at 400 to 600 C and at pressures of 1 1/4, 5, and 10 tsi. The origin of the macroscopic defects occurring in the UAl/sub 3/ layer during interdiffusion was clarified. The solubility range of UAl/sub 3/ was determined by a nuclear track emulsion technique to be about 2.6 at.% uranium. Exploratory runs… more
Date: June 30, 1959
Creator: Castleman, L.S. & Seigle, L.
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Hazards and Safety Measures Related to Nuclear-Powered Merchant Ships: An Annotated Bibliography of Declassified Literature

Description: This compilation contains 202 abstracts of reports and documents on subjects related to maritime reactor safety; the abstracts are indexed in thc AEC Abstracts of Classified Reports'' (ACR). These ACR references were listed as unclassified or declassified in TID-4021, TID-40.35, and TID-4035, Supplement 1. The abstracts were selected as a part of the preparation of the classified bibliography (ALI-50, printed August 30, 1958) on this same subject. (See also SO-6200, Septcmber 15, 1957, unclassi… more
Date: March 30, 1959
Creator: White, M. K.
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Heat Transfer in Septafoil Geometries by Mass-Transfer Measurements

Description: In conjunction with Gas-Cooled Reactor heat-transfer studies, local and mean heat-transfer factors are predicted from the heat transfer-mass transfer analogy using subliming naphthalene in air. Experimentation was conducted on 1-in.-dis septafoil rods in a 4-in. -dis flow channel with rod center-to center spacings of 1.10, 1.25, and 1.40 in. at a Reynolds modulus of approximately 60,000. Ratios of local mass transfer to mean mass transfer for a given rod vary as much as from 0.7 to 1.3 (outer r… more
Date: June 30, 1959
Creator: Wantland, J. L. & Miller, R. L.
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