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LEAKAGE OF WATER FROM GASKETED JOINTS PROPOSED FOR THE HWCTR. PART I

Description: When mockups of typical gasketed joints proposed for the HWCTR were subjected to thermal and pressure cycling that simulated reactor operating conditions, the average leakage rate was less than 0.11 lb of water per year per linear inch of gasket. The joints were exposed to deionized light water and were cycled 100 times from about 70 deg C and atmospheric pressure to 250 deg C and 1000 psig. (auth)
Date: July 1, 1960
Creator: Apple, F.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRELIMINARY HAZARDS EVALUATION OF THE ISOLATED COOLANT LOOPS IN THE HWCTR

Description: The design features of two isolated coolant loops in the Heavy Water Components Test Reactor (HWCTR) and the effect of these features on reactor safety are described. It is shown that limitations on the operating conditions, backed up by properly chosen safety systems, will permit operation of the loops without adding appreciably to the reactor hazards. (auth)
Date: July 1, 1960
Creator: Arnett, L.M.; Parkinson, T.F.; Randall, D. & Ross, C.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Consolidated Edison Thorium Reactor Critical Experiments With Oxide Fuel Pins

Description: Critical experiments with pin-type oxide fuel elements for the CETR are described. These experiments were conducted to provide data on the infinite medium properties of the lattice inside the canned elements in the various CETR loading zones and to obtain specific information on the fullsize CETR core. Measurements are described and results are interpreted. (J.R.D.)
Date: July 1, 1960
Creator: Batch, M. L. & Snidow, N. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Materials Study. Research and Development of Metal Hydrides. Quarterly Report No. 7 for April 1, 1960 to June 30, 1960

Description: High-temperature x-ray diffraction experiments provided confirming evidence regarding the origin of the metastable gamma phase and of the general features of the zirconiumhydrogen phase system. These experiments also showed that the reaction alpha + delta -- beta (the eutectoid reactlon on heating) proceeds at an extraordinarily slow rate, although the reverse reaction proceeds so rapidly that beta phase cannot be retained to room temperature by quenching. The sluggishness of the eutectoid reac… more
Date: July 1, 1960
Creator: Beck, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cost Study of a 100-Mw(E) Direct-Cycle Boiling Water Reactor Plant

Description: A technical and economic evaluation is presented of a direct-cycle light- water boiling reactor designed for natural circulation and internal steam-water separation. The reference lOO-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. (W.D.M.)
Date: July 1, 1960
Creator: Bullinger, C. F. & Harrer, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

TEST OF GERMAN UNDERGROUND PERSONNEL SHELTERS

Description: The predicted behavior of German underground personnel shelters, equipment, and certain instrumentation was investigated. Data obtained will be used for evaluation and improvement of present design criteria. Nine reinforcedconcrete underground shelters, designed by German engineers, were tested at the 170-, 155-, 110-, 78-, 26-, 11.5-, and 7.2-psi overpressure ranges as determined from average blast-line instrumentation measurements. Reinforcing steel, doors, and ventilation equipment were rece… more
Date: July 1, 1960
Creator: Cohen, E. & Bottenhofer, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CHEMICAL DECONTAMINATION OF THE ANL-2 HIGH-PRESSURE WATER LOOP

Description: The chemical decontamination of the ANL-2 Highpressure Water Loop at the MTR is described. A mixture of sodium hydroxide and potassium permanganate was first applied to oxidize partially and loosen the magnetite corrosion film on the loop surfaces. Next, the system was treated with a solution of Versenol 120 to remove and suspend the loosened oxide film. The third chemical treatment was a mixture of sulfamic acid, HEDTA, hydrazine, and Rodine 80. After the first two chemical treatments a brown … more
Date: July 1, 1960
Creator: Crothers, C.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JUNE 1960

Description: Solid solutions of uranium oxide containing massive additions of La/sub 2/O/sub 3/ or Y/sub 2/O/sub 3/ are being investigated with respect to their stability in an oxidizing environment at higher temperatures. An investigation is being conducted on the effects of ultrahigh pressure and high temperature on the U-O system and on reactions of uranium oxides with various mixed oxides. Work was continued on the investigation of the effects of fast-neutron irradiation upon the mechanical properties o… more
Date: July 1, 1960
Creator: Dayton, R.W. & Tipton, C.R. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermal and Hydraulic Design of the Consolidated Edison Thorium Reactor

Description: ABS>The thermal and hydraulic analyses, both steady state and transient for the CETR are presented. Methods of calculations are discussed and results of analyses are presented. Steady-state analyses are included for pressure drops, flow distribution, orificing, burnout, fuel and burnout cannot occur at any attainable reactor power in the CETR as designed. Bulk boiling of the coolant does not occur at any point in the core during normal steadystate operation. Bulk boiling is permitted during tra… more
Date: July 1, 1960
Creator: Ferrell, J. K.; Flora, H. E.; Hostetler, D. R.; Stanek, L. J. & Vannoy, W. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Consolidated Edison Thorium Reactor-Reactor Vessel Internal Components Design

Description: The design functions and fabrication details for internal components of the CETR are presented and pertinent analytical stress studies are summarized. Functions of the internal components include proper orientation and support for the fuel elements, proper distribution of primary coolant within the reactor vessel, and the establishment of guide channels for the control rods. (J.R.D.)
Date: July 1, 1960
Creator: Ficor, J.; Collings, D. M.; Sandrock, R. J. & Kalen, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

COULOMETRIC TITRATION OF URANIUM IN NITRIC ACID SOLUTIONS

Description: A coulometric titration method was developed for the determination of uranium in HNO/sub 3/ solutions. Uranium was reduced to the (IV) state and was titrated with electrolytically generated cerium(IV). The colorimetric end point was detected automatically by a photometric technique. Interference from nitrate was eliminated by the addition of urea to the titration medium. The coefficient of variation for the analysis of uranium was 3.2% for 1-mg samples and 0.3% for 100-mg samples. With the addi… more
Date: July 1, 1960
Creator: Fulda, M.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Irradiation of an Aluminum Alloy-Clad, Aluminum-Uranium Alloy-Fueled Plate

Description: Irradiation tests of an aluminum-alloy-clad aluminum -urantum alloy- fueled plate were discontinued due to cladding failure after a maximum burnup of 58%. Cause of the failure was local corrosion of the aluminum alloy. Swelling was observed which was attributed to the combination of bigh burnup and high fuel temreratures. (C.J.G.)
Date: July 1, 1960
Creator: Gavin, A.P. & Crothers, C.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

TRIP-1--A TWO-DIMENSIONAL P-3 PROGRAM IN X-Y GEOMETRY FOR THE IBM-704

Description: The TRlP-1 program was designed to solve the onegroup P/sub 3/ equations in XY geometry. It was used to investi gate solutions to two-dimensional transport effects. The program is a modified version of PDQ-3. (auth)
Date: July 1, 1960
Creator: Gelbard, E.; Davis, J.; Dorsey, J.; Mitchell, H. & Mandel, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

[Georg Kolbe Sculpture]

Description: Photograph of a Georg Kolbe sculpture in Rotterdam, Netherlands. In the foreground, the sculpture is positioned on a grassy bank by a canal; the canal and trees are visible in the background. The photograph was taken in the Het Park during the Floriade Festival.
Date: July 1, 1960
Creator: Gough, Ray
Item Type: Refine your search to only Photograph
Partner: UNT College of Visual Arts + Design

[Henry Moore Sculpture]

Description: Photograph of a Henry Moore sculpture in Rotterdam, Netherlands. In the foreground, the sculpture sits on a concrete pedestal; trees, grass, and other sculptures are visible in the background. The photograph was taken in the Het Park during the Floriade Festival.
Date: July 1, 1960
Creator: Gough, Ray
Item Type: Refine your search to only Photograph
Partner: UNT College of Visual Arts + Design

[Henry Moore Sculpture]

Description: Photograph of a Henry Moore sculpture in Rotterdam, Netherlands. In the foreground, the sculpture and a tree stand in front of a hedge; rows of tall trees are visible in the background. The photograph was taken in the Het Park during the Floriade Festival.
Date: July 1, 1960
Creator: Gough, Ray
Item Type: Refine your search to only Photograph
Partner: UNT College of Visual Arts + Design
open access

Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1960 - June 1, 1960

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: July 1, 1960
Creator: Hardy, Edward P., Jr.; Klein, Stanley & Rivera, Joseph
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HEAVY WATER MODERATED POWER REACTORS PROGRESS REPORT FOR MAY 1960

Description: BS>A Zircaloy-clad tube of unalloyed uranium that was irradiated in a loop of the NRU reactor to a maximum exposure of 950 Mwd/ton at a maximum uranium temperature of 40O deg C experienced less than 1.5% volume increase and 0.14% outer-cladding strain. Inspection of the swaged oxide tube that had failed during irradiation in a Savannah River reactor revealed that a 9-in.-long crack of as-yet-unknown origin had developed in the outer stainless-steel cladding of the tube. Transient calculations s… more
Date: July 1, 1960
Creator: Hood, R.R. & Isakoff, L. comps.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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