Potential Applications of Nuclear Energy in a Marine Environment (open access)

Potential Applications of Nuclear Energy in a Marine Environment

Introduction: In January 1959, Stanford Research Institute was asked by the Office of Maritime Reactors, Division of Reactor Development, of the United States Atomic Energy Commission to identify potential applications of nuclear energy in a marine environment, excluding those involving standard commercial surface ships and direct defense applications, and to conduct a preliminary evaluation of these applications in order to determine which ones appeared most feasible for early implementation.
Date: August 1959
Creator: Duckstad, Eric E.
System: The UNT Digital Library
Surface Motions from a Series of Underground Nuclear Tests (open access)

Surface Motions from a Series of Underground Nuclear Tests

Abstract: Ground effects resulting from Blanca, Logan, Evans, Tamalpais and Mars events of HARDTACK Phase II underground explosions were measured by strong-motion and teleseismic seismographs out to distances of nearly 100 miles.
Date: August 10, 1959
Creator: Carder, D. S.; Cloud, W. K.; Pearce, T. H. & Murphy, L. M.
System: The UNT Digital Library
Nuclear Merchant Ship Reactor Shield Design Summary Report (open access)

Nuclear Merchant Ship Reactor Shield Design Summary Report

Abstract: "Most of the Nuclear Merchant Ship Reactor (NMSR) shield design work performed by The Babcock & Wilcox Company (B&W) is summarized. Primary and secondary shield results are presented, consistent with contractual requirements and designated design criteria. Methods of calculation and basic parameters are shown" (p. 1).
Date: August 1, 1959
Creator: Smith, W. R. & Turner, M. A.
System: The UNT Digital Library
A Test for Electron Transfer in the Intermetallic Compound, V4Al23 (open access)

A Test for Electron Transfer in the Intermetallic Compound, V4Al23

Abstract: "Abnormally short interatomic distances are characteristic of aluminum-transition element compounds which occur at the aluminum-rich ends of the phase diagram." Summary: "The theoretical model assumed in this investigation was that of spherical distribution of electrons centered about atomic sites in the V4Al23 structure, represented by the theoretical scattering factors for the isolated atoms. ...It is evident from the (Fo-Fc)-synthesis maps that too much scattering power has been assumed in the immediate vicinity of each atomic site since the negative regions associated with these sties represent electron density differences which are generally two to three times greater than the estimated experimental errors. ...An estimate of the number of electrons associated with the positive regions in the (Fo-Fc)-synthesis maps, and presumably the number of electrons participating in the bonding, could be obtained by computing structure facts with theoretical scattering factors which account for the contributions of the core electrons only. An (Fo-Fc)-synthesis with these Fc values and the Fo values from this investigation should then approximate the actual distribution of the outer electrons."
Date: August 1959
Creator: Ray, Alden Earl & Smith, J. F.
System: The UNT Digital Library
Nonlinear Analogue to Digital Converter (open access)

Nonlinear Analogue to Digital Converter

Technical report. From Abstract: "An electromagnetical instrument is described which produces a shaft rotation which is a linear function of the quantity being measured from a non-linear input signal. The instrument was used to convert the output function of the Nuclear Test Gage (NTG) which is nonlinear with respect to fuel concentration to a form that will directly drive an automatic production recorder (APR). The output shaft is also geared to a Veeder Root counter so that the value of the independent variable is given to the NTG operator in digital form. A rate-of-change detector automatically trips the APR when the reading has come sufficiently close to equilibrium."
Date: August 1959
Creator: Goodwin, Leslie E.
System: The UNT Digital Library
SM-1 Research and Development Program, Activity Buildup Program Task 1 : final report February 1958 to June 1959 (open access)

SM-1 Research and Development Program, Activity Buildup Program Task 1 : final report February 1958 to June 1959

Abstract: The results of activity buildup studies in the SM-1 (APPR-1) performed from February 1958 to January 1959 are reported. Data are presented on the extent, nature, and mechanism of the buildup of long-lived gamma emitting nuclides in the reactor primary system. Mathematical equations to describe the activity buildup are derived. Radiation levels after reactor shutdown are presented, as well as the predicted radiation levels at the end of core life.
Date: August 10, 1959
Creator: Brown, William S.; Bergen, C. Richard.; Bergmann, Carl A.; Chupak, Julius.; Fitzsimmons, Susanne R. & Grant, Louis G.
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: February-April 1959 (open access)

Homogeneous Reactor Project Quarterly Progress Report: February-April 1959

Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.
Date: August 8, 1959
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Technical Progress Report, University of Illinois, Graduate College, Digital Computer Laboratory, August 1959 (open access)

Technical Progress Report, University of Illinois, Graduate College, Digital Computer Laboratory, August 1959

This technical report covers five areas: (1) High-speed computer program; (2) Mathematical methods; (3) ILLIAC use and operations; (4) IBM 650 use and operation; (5) General laboratory information.
Date: August 1959
Creator: Taub, A. H., 1911-1999
System: The UNT Digital Library
Melting Point of Th-U-C Fuel Elements (open access)

Melting Point of Th-U-C Fuel Elements

From the point of view of predicting melting behavior of fuel elements containing fission products after 50 percent burn-up, the fuel can be considered to consist of 2000 moles Th, 150 moles U, 55 moles of rate earth metal, 31 moles of Zr, 25 moles of Mo, 20 moles of Rh-Ru-Tc, and 15 moles of alkaline earth metal. All other fission products are present in too small amounts to have any important effect upon the melting point or will have vaporized. However, the presence of alkali metal vapor should be considered.
Date: August 3, 1959
Creator: Brewer, Leo, 1919-2005
System: The UNT Digital Library
Fate of Fission Product Gases in the Coolant Stream (open access)

Fate of Fission Product Gases in the Coolant Stream

The quantity and characteristics of fission products in coolant gases due to leaking fuel elements are discussed. It is concluded that the rare gases, the alkali metals, the halides, and Sb may act as permanent gases to a considerable extent. The other fission products are expected to condense out completely on walls or as dust consisting of metals, carbides, and oxides.
Date: August 4, 1959
Creator: Brewer, Leo, 1919-2005
System: The UNT Digital Library
Heat Transfer Fluids for Fuel Element Cans (open access)

Heat Transfer Fluids for Fuel Element Cans

The maximum temperature in the interior of the fuel element could be greatly reduced by incorporating a liquid between the fuel element and the outer can to increase-heat transfer rates. It is of interest to consider what liquids would be chemically compatible with graphite and the actinide carbides. Elements which melt below 1100 and boil above 1400 deg C that form no stable solid carbides, include Cu, Ga, TI, Ge, Sn, Pb, Sb, Bi, and compounds include GeP, GeS, GaP, Ga/sub 2/S, GaTe, GaAs, SnTe, Sm/sub 3/As/sub 2/, Sb/sub 3/Te/sub 2/, Zn/sub 3/Sb/sub 2/, Zn/sub 3/P/sub 2/, ZnS, ZnTe, and Zn/s ub 3/As/sub 2/. Some of these compounds have equilibrium pressures that might be considered too high, but they may actually vaporize slowly enough because of low vaporization coefficients to make them suitable. There are probably rot enough data nor adequate theories for predicting the rates, and Langmuir type vaporization experiments would be necessary to determine the rates of vaporization of these compounds. The main problem in the use of a heat transfer fluid is that of reaction between the fluid and the actinide carbides. Thermodynamically extensive attack would be expected. However, it may be possible to make the rate …
Date: August 4, 1959
Creator: Brewer, Leo, 1919-2005
System: The UNT Digital Library
Vaporization Processes in a Runaway Reactor (open access)

Vaporization Processes in a Runaway Reactor

From the point of view of constituents of a fuel element at temperatures between 2500 and 4500 degree K, the fuel elements can be considered to consist of six types of material: carbon, elements less volatile than carbon, 26 moles of rare gases, 21 moles of alkali metals, 17 moles of alkaline earth metals, and 4 moles of miscellaneous volatile elements. Various processes involving the constituents from 2000 to 45000 degree K are considered. Reactivity gain due to can rupture is discussed.
Date: August 4, 1959
Creator: Brewer, Leo, 1919-2005
System: The UNT Digital Library