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  Partner: UNT Libraries Government Documents Department
 Decade: 1950-1959
Revised Reactor Fuel and Fuel Processing Costs - July 1953

Revised Reactor Fuel and Fuel Processing Costs - July 1953

Date: July 10, 1953
Creator: Wheelock, C.W.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Feasibility of Various Types of Seals for the Carrier Freon 11 Turbocompressors

Feasibility of Various Types of Seals for the Carrier Freon 11 Turbocompressors

Date: May 1, 1952
Creator: none
Description: A preliminary feasibility study is made of seals for a machine running at 8000 rpm, having a 2-in. shaft, and operating with a pressure differential of 5 lb/in{sup2}. The following conditions must be met: during operation the air inleak shall not exceed 50 lb/2000 hr and the loss of Freon 11 shall not exceed 0.02 lb/hr; the leak-up rate during shutdown shall not exceed 1/10 in. of Hg per 24 hr (the contained volume is 100 ft{sup3}). Dry-contact and Freon 11-lubricated contact seals are considered briefly, but neither appears to be practical. The following positive-clearance seals are more feasible and are discussed in greater detail: concentric-cyinder seal, utilization of a journal bearing of the machine as a seal, and a radial-controlled-gap type of seal.
Contributing Partner: UNT Libraries Government Documents Department
ENVIRONMENTAL CONTAMINATION FROM WEAPON TESTS

ENVIRONMENTAL CONTAMINATION FROM WEAPON TESTS

Date: October 1, 1958
Creator: none
Description: The program of the Atomic Energy Commission on environmental contamination from weapons tests is designed for the overall evaluation of the hazard to humans from test operations. It is limited to studies of the deposition of activity at long range rather than the problems associated with immediate, close-in fallout. The program has largely been a study of Sr{sup 90}, since considerations based on experience and measurement indicate that it is the isotope of greatest potential hazard. Data are presented pertinent to the monitoring of long-range fallout, particularly Sr{sup 90} and Cs{sup 137}. Values are tabulated for the fallout deposition, air concentrations, water concentrations, and the amounts in foods and human bone. In addition, results are given for some experimental investigations. The report of these results is not interpretative although certain papers that do attempt to interpret the present situation with respect to Sr{sup 90} in particular are reprinted. Bibliographies are presented covering the period since the 1957 hearings before the Joint Committee on Atomic Energy concerning the nature of radioactive fallout and its effects on man. A document list of submissions to the United Nations Scientific Committee on the Effects of Atomic Radiation is given to illustrate the work done ...
Contributing Partner: UNT Libraries Government Documents Department
Special Purpose Power Plant Critical Facility Summary Hazards Report (Addendum 2)

Special Purpose Power Plant Critical Facility Summary Hazards Report (Addendum 2)

Date: March 11, 1959
Creator: Thiele, A.W.
Description: The SNAP Experimental Reactor (SER) is a small power reactor that is to be built and operated in the original SNAP-II critical facility. The reactor is described, and the hazards previously evaluated for the SNAP II critical faciity are reviewed.
Contributing Partner: UNT Libraries Government Documents Department
Project Proposals and Authorization-Budget Estimate for Fiscal Year 1953

Project Proposals and Authorization-Budget Estimate for Fiscal Year 1953

Date: January 29, 1952
Creator: Starr, C. & Waite, L.L.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
MACHINING TECHNIQUES AND PROCEDURES FOR URANIUM, GRAPHITE, TITANIUM, ZIRCONIUM, THORIUM, TANTALUM, BERYLLIUM, BISMUTH, LITHIUM, AND STELLITE

MACHINING TECHNIQUES AND PROCEDURES FOR URANIUM, GRAPHITE, TITANIUM, ZIRCONIUM, THORIUM, TANTALUM, BERYLLIUM, BISMUTH, LITHIUM, AND STELLITE

Date: November 4, 1952
Creator: Davis, C.
Description: Techniqnes are presented which are applicable in machining materinls such as U, graphite, Ti, Zr, Th, Ta, Be, Bi, Li, and stellite. Included in the general considerations are factors related to machinability of the materials, operating condition of the machines, and the condition of the cutting tools. In addition, industrial hygtene and safety aspects are examined. The techniques for each material are discussed in detail, the greatest attention being focused on uranium.
Contributing Partner: UNT Libraries Government Documents Department
Performance Parameters Pertinent to Nuclear Powered Aircraft

Performance Parameters Pertinent to Nuclear Powered Aircraft

Date: February 6, 1952
Creator: Ruffman, B.F.
Description: A review of the present design information and studies relating to nuclear power plants indicates that the weight of the power plant components, exclusive of crew shield and nacelles, may at a particular design point be represented by an equation of the form, W{subpp} = W{subo} + K{subt}T. By use of this, a power plant parameter psi is defined as the ratio of the part of the power plant plus nacelle weight that varies with thrust to the net thrust of the power plant less nacelle drag. The funamentall part that this parameter plays in determining the gross weight of a nuclaer powered aircraft is shown. This parameter depends on the design point Mach number and altitude, and the weight and drag increments attributable to the nacelle installation.
Contributing Partner: UNT Libraries Government Documents Department
Evaluation of NaK as the Primary Coolant for the SNAP II System

Evaluation of NaK as the Primary Coolant for the SNAP II System

Date: July 10, 1959
Creator: Wallerstedt, R.
Description: An evaluation was made of the use of NaK as the primary coolant for the SNAP-2 system. Pumping-power limitations based on the mercury Rankine cycle are analyzed. Problems pertinent to any design-specification modifications are reviewed.
Contributing Partner: UNT Libraries Government Documents Department
Reflector Moderated Solid Fuel Element Sodium Cooled Reactor Critical Mass vs. Power Density

Reflector Moderated Solid Fuel Element Sodium Cooled Reactor Critical Mass vs. Power Density

Date: September 6, 1955
Creator: Merriman, F.C. & G., Chase
Description: This is the sixth of seven reports to be issued on the parametric studies of reflector-island moderated and core moderated solid fuel element reactors. The power distribution and hence fuel volume were varied for the optimum island size reflector moderated reactor. The effect on the critical mass, power distribution and neutron leakage was determined and is plotted in Figures 1, 2, and 3.
Contributing Partner: UNT Libraries Government Documents Department
Inside Cooling of Square Fuel Elements, I.

Inside Cooling of Square Fuel Elements, I.

Date: March 24, 1952
Creator: Chrisney, J.B.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
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