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COMPARISON OF BULK SHIELDING REACTOR CENTERLINE MEASUREMENTS IN WATER WITH PREDICTIONS

Description: Measurements of fast neutron and gamma ray dose rates in water along the centerline of the Bulk Shielding Reactor (BSR) are compared with predictions made by use of three available computer programs. It is found that the predictions are very dependent on the assumptions made concerning power distribution and that the more accurate descriptions of the source lead to predictions that agree with measurements to within 20% throughout thickness ranges as great as 100 centimeters of water. (auth)
Date: November 1, 1958
Creator: Casper, A.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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APPR-1 BURNOUT CALCULATIONS

Description: A general non-uniform burnup program was developed to determine the lifetime of the APPR-1. The calculation is performed using two one dimensional multi-region burnout calculations. The approach to the problem, the equations, and derivation of burnout equations are presented. The results are plotted and compared with the rod bank position as measured at Fort Belvoir. On the basis of these calculations the expected total energy release of the APR-1 is 13 Mw-yr. (auth)
Date: April 10, 1958
Creator: Williamson, T. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Performance of Basic XJ79-GE-1 Turbojet Engine and Its Components

Description: Memorandum presenting an investigation to determine the performance of the XJ79-GE-1 turbojet engine and its components, while operating as integral parts of the engine, conducted in an altitude test chamber. Data were obtained over a range of Reynolds number indices and for various settings of the variable compressor stators and variable-area exhaust nozzle from fully open to fully closed positions. Results regarding the component performance and engine performance are provided.
Date: May 8, 1958
Creator: Campbell, Carl E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurements of the Buffeting Loads on the Wing and Horizontal Tail of a 1/4-Scale Model of the X-1E Airplane

Description: "The buffeting loads acting on the wing and horizontal tail of a 1/4-scale model of the X-1E airplane have been measured in the Langley 16-foot transonic tunnel in the Mach number range from 0.40 to 0.90. When the buffeting loads were reduced to a nondimensional aerodynamic coefficient of buffeting intensity, it was found that the maximum buffeting intensity of the horizontal tail was about twice as large as that of the wing. Comparison of power spectra of buffeting loads acting on the horizont… more
Date: September 17, 1958
Creator: Rainey, A. Gerald & Igoe, William B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Incipient spin characteristics of a 1/25-scale model of the Chance Vought XF8U-1 airplane: TED No. NACA AD 3118

Description: Report presenting an investigation of the incipient spin characteristics of a 1/25-scale dynamic model of the Chance Vought XF8U-1 airplane. The model was launched by a catapult apparatus into free flight at the angle of attack and airspeed correspond to stall with various control settings and was loaded as lightly as possible because of the limitations of the catapult apparatus. Results regarding the basic data and effects of modifications are provided.
Date: April 17, 1958
Creator: Healy, Frederick M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ALUMINUM DETERMINATION IN REACTOR COOLING WATER

Description: ABS>A method for determination of submicrogram quantities of Al in reactor cooling water by neutron activation analysis is described. Data obtained in analyses of samples from the OKR and the Bulk Shielding Reactor are included. (J.R.0.)
Date: September 1, 1958
Creator: Emery, J.F. & Leddicotte, G.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ESTIMATE OF THE RATIO OF Ta$sup 182$ TO Co$sup 60$ ACTIVITY EXPECTED IN THE APPR-1 CORE

Description: S>Of primary interest in a military reactor is the desirability of quick and easy maintenance of as much of the system as possibie throughout the lifetime of the power plant. It is therefore desirable that no serious amounts of long- lived activity build up in equipment outside the core. An investigation was made to determine the activity due to small amounts of cobalt and tantalum in the stainless steel core of the APPR-1. The investigation indicates that equal weight percentages of Ta and Co … more
Date: February 10, 1958
Creator: Gross, E.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRESSURIZATION OF HRE-3 WITH AN OXYGEN-INERT GAS MIXTURE

Description: Calculations made on the possibility of pressurizing HRE-3 with oxygen- helium and oxygen-argon mixtures indicate that such a system is feasible, but not necessarily more desirable than use of oxygen alone. The explosion hazard would not be reduced significantly by use of the inert gas and the off-gas design problems would be somewhat more difficult. (auth)
Date: April 15, 1958
Creator: Hilvety, N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRE-3 Blanket Heat Exchanger as a Feedwater Reactor Rather Than as a Steam Generator

Description: There may be an advantage to designing the HRE-3 vertical shell and tube slurry heat exchanger as a feedwater heater rather than as a steam generator from the standpoint of space requirement and blowdown problems. This study of the effect of this arrangement on the thermal efficiency of the heat-power cycle indicates that the gross electrical generating capacity of HRE-3 would be reduced by about 500-kw, or about 3 to 4% of the output. It is concluded that, (a) there is sufficient merit in usin… more
Date: April 14, 1958
Creator: Robertson, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation of Prototype CP-4 (EBR-I) Reactor Fuel Slugs in the CP-3' Goat Hole. Final Report of Metallurgy Division Program 6.1.1.

Description: Experiments are described which studied the effect of irradiation upon small U/sup 235/ cylinders simulating in size those designed for thc initial CP-4 (EBR-I) fuel loading. Qualitative similarities between thermal cycling and irradiation effects were found, but none of the three types of inaterial tested were entirely dimensionally stable. (auth)
Date: August 1, 1958
Creator: Paine, S. H.; Persiani, P. J. & Murphy, W. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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POWER BURSTS IN NUCLEAR REACTORS

Description: It is shown that some of the properties of a power burst in a reactor are independent of either the feedback mechanism or the pile kinetics, and may be described quantitatively with no assumption other than that the pile kinetic equations are nonlinear. The theory refers primarily to the shape of the burst and is applicable chiefly to the faster transients observed in SPERT, KEWB, and B0RAX. The data which may be described theoretically in this manner include plots of maximun reactor power time… more
Date: September 1, 1958
Creator: Corben, H.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Critical Experiments With Arrays of Orr and Bsr Fuel Elements

Description: Critical experiments were performed with ORR and BSR fuel elements to determine safe arrays in which the elements could be handled and stored. The data indicate that the optimum spacing for criticality of 168-g ORR elements in water is 0.2 in. between locating bosses annd that an infinite array of vertically placed elements onc element high would probably be subcritical with a 1 1/2-in. spacing between locating bosses. For uniform arrays of adjacent elements in water, variation in thc fuel load… more
Date: October 1, 1958
Creator: Fox, J. K. & Gilley, L. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Temperature Coefficient Measurements on a Critical Mock-Up of EBR-I

Description: A rough mock-up of the EBR-I reactor was built in the ZPR-III critical assembly machine, with resistance heaters in the core and inner blanket. The variation of reactivity with core temperature was observed. Lateral expansion was measured as the core was heated. A temperature coefficient of --0.42 inhour per degree Centigrade was observed when the core alone was heated, and --0.72 inhour per degree Centigrade was observed when the core and inner blanket both were heated. Essentially all of thes… more
Date: March 1, 1958
Creator: Long, J. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MATERIAL SPECIFICATIONS FOR APPR-1 CORE II CONTROL ROD FUEL ELEMENTS AND ABSORBER SECTIONS

Description: The control rod fuel elements consist of 16 flat composite fuel plates joined to a pair of side plates to form an integral assembly with a nominal water gap spacing of 0.133 inches between fueL plates. The core section of the fuel plate contains an active fuel section and a flux suppressor section. The fuel section is composed of UO/sub 2/, B/sub 4/C, and type 304LB stainless steel. The suppressor section is composed of Eu/sub 2/O/sub 3/ and elemental stainless steel powder. The absorber sectio… more
Date: December 30, 1958
Creator: Edgar, E.C. & Robertson, R.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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INTEGRAL FLUX SUPPRESSOR FOR APPR-1, CORE II

Description: An internal flux suppressor will be used for the APPR-1 Core II instead of the external suppressors that are employed in Core I. The reference design of the integral flux suppressor for Core II is as follows: materials Eu/sub 2/O/sub 3/ in stainless steel matrix; compositions 23.2 wt.% Eu/sub 2/O/sub 3/; and dimensions, 0.02 in. x 2.281 in. x 0.875 in. The survey on the cffectiveness of this referencc design has shown that thc peaking of the flux in the control rod fuel element tip is eliminate… more
Date: April 10, 1958
Creator: Leibson, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EBR-I, MARK III-DESIGN REPORT

Description: Under severe operating conditions, the Experimental Breeder Reactor was observed to exhibit oscillatory power characteristics and periods of prompt positive reactivity. Investigations of these characteristics resulted in the meltdown of Core-II and the design of a more suitable Core-III, with rod bowing eliminated and greater coolant flow control. The design of the core. rods, assemblies. and matrices is presented, and its control and cooling systems are described. (D.E B.)
Date: March 1, 1958
Creator: Rice, R.E.; Curran, R.N.; McGinnis, F.D.; Nevick, M. & Thalgett, F.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Further Studies With the GCRE Critical Assembly

Description: Further engineering and physics data to aid in constructing GCRE-1 were obtained in critical-assembly studies. Four major experiments were performed to investigate the effect on reactivity caused by changes in axial reflector materials, the effect on reactivity and the power perturbation caused by fast safety control-blade guides, the effect of changes in fuel-element material composition, and the effect of changes in fuel-element spacing designed to produce uniform radial power-generation rate… more
Date: December 29, 1958
Creator: Dingee, David A.; Ballowe, William C.; Egen, Richard A.; Jankowski, Francis J. & Chastain, Joel W., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SUMMARY OF HRE-2 RUN 13 (INITIAL POWER OPERATION)

Description: The first power operation of the HRE-2, referred to as Run 13, occurred in February 1958. In five days of power operation, the maximum sustained power was 1.5 Mw and the total power generated was 4B Mw-hr. During the first part of the power operation, the fuel solution contained very little internal recombination catalyst. This part of the run was characterized by high concentrations of radiolytic gas and significant loss of reactivity at very low powers. After an addition of copper and acid, r… more
Date: October 29, 1958
Creator: Engel, J.R.; Haubenreich, P.N.; Hernandez-Fragoso, J. & Richardson, D.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Specifications and Fabrication Procedures for APPR-1 Core II Stationary Fuel Elements

Description: Stainless steel-base fuel components of thin plate-typs construction and containing a dispersion of enriched UO/sub 2/ have been successfully employed in powering the Army package Power Reactor. The stationary fuel compcnent proposed for operation in the second core loading of the reactor is discussed. The component is designed for radioactive service in pressurized water at 4504DEF and consists of eighteen composite fuel plates joined into an Integral unit or assembly by brazing. Design specif… more
Date: July 15, 1958
Creator: Cunningham, J. E. & Beaver, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THERMAL DESIGN CRITERIA FOR APPR PRESSURIZED WATER REACTORS

Description: The criteria established for thermal design of APPR pressurized water reactors are given. These include heat transfer coefficient, power distribution utillzation, hot channel factors, lattice requirements, and instrumentation tolerances. Calculations are shown for hot channel factors, lattice requirement determination, and heat release distribution. (T.R.H.)
Date: November 26, 1958
Creator: Love, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A method for rapid selection of design characteristics of 1-, 1 1/2-, and 2-stage turbines with optimum annulus taper

Description: Report presenting a method for the rapid selection of a turbine design within specified aerodynamic limits. Tables are provided with the overall design parameters and velocity-diagram variables of each design. Detailed design information is also included for ranges of blade-speed parameter and exit radius ratio.
Date: February 18, 1958
Creator: Yohner, Peggy L. & English, Robert E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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