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Fast Flux Test Facility Studies Progress Report: April 1965

Description: From abstract: "...limited study work was performed on the conceptual design of the proposed fast flux test facility and information was obtained in important areas of supporting technology."
Date: April 1965
Creator: Astley, E. R.
Partner: UNT Libraries Government Documents Department
open access

A Sequence for Predicting Waste Transport by Ground Water

Description: From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date: April 15, 1965
Creator: Nelson, R. William
Partner: UNT Libraries Government Documents Department
open access

Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel

Description: The experiments described in this report were performed for two purposes: (1) to find a chemical, or combination of chemicals, that would be effective for inhibiting corrosion of steel in static portions of the Hanford water systems, and (2) as screening tests to select candidate mixtures for further testing to replace sodium dichromate as the inhibitor of aluminum and steel corrosion in the Hanford single-pass reactor cooling water.
Date: February 1965
Creator: Richman, R. B.
Partner: UNT Libraries Government Documents Department
open access

Final Report: Investigation of Boiling Flow Regimes and Critical Heat Flux

Description: From abstract: A program to investigate the mechanism of the critical heat flux condition from the standpoint of flow regimes has been initiated at Dynatech for the AEC. This report covers the work done on this investigation in the first year.
Date: March 1, 1965
Creator: Suo, M.; Bergles, Arthur E.; Doyle, Edward F.; Clawson, L. & Goldberg, P.
Partner: UNT Libraries Government Documents Department
open access

The Development of an Improved Thermionic Energy Converter: Third Quarterly Technical Report

Description: From introduction: The objective of the current program is to determine the feasibility of the reservoirless converter operation by conducting a series of tests on operating thermionic converters which contain cesium in the vapor phase only.
Date: April 1965
Creator: Radio Corporation of America. Direct Energy Conversion Department.
Partner: UNT Libraries Government Documents Department
open access

SRE Mark II Fuel Handling Machine

Description: Abstract: The Sodium Reactor Experiment Mark II Fuel Handling Machine has been modified to ensure fuel and gas containment during core III operation. A new fuel control system has been designed for the fuel handling machine.
Date: April 20, 1965
Creator: Dietz, H. B.
Partner: UNT Libraries Government Documents Department
open access

SNAP 10A FSEM-3 Agena Compatibility Test

Description: From abstract: This report summarizes the results of SNAP-10A/Agena developmental testing and final vehicle systems tests.
Date: June 15, 1965
Creator: Teresa, M.
Partner: UNT Libraries Government Documents Department
open access

The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1

Description: Abstract: Atomics International conducted a fuel irradiation program to investigate and define the behavior of U-10 Mo fuel at the temperatures and fission rates anticipated in Hallam Nuclear Power Facility (HNPF) Core I.
Date: February 1, 1965
Creator: Schmitt, A. R.; Willard, R. M. & Magnus, D. K.
Partner: UNT Libraries Government Documents Department
open access

The Properties and Irradiation Behavior of U₃Si₂

Description: Abstract: A limited study of the compound U₃Si₂ has been made in reference to its use as a prospective nuclear fuel in sodium cooled reactors.
Date: July 25, 1965
Creator: Shimizu, H.
Partner: UNT Libraries Government Documents Department
open access

Carbide Fuels in Fast Reactors

Description: Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.
Date: September 15, 1965
Creator: Wheelock, C. W.
Partner: UNT Libraries Government Documents Department
open access

U-10 Wt % Mo Fuel Element: Irradiation in SRE

Description: From abstract: The fuel element assembly was successfully irradiated in the SRE to a maximum burnup of 5300 Mwd/MTU, at a peak fission rate of approximately 1.5 x 10E13 fissions/cm3-sec and a maximum central temperature near 1200F.
Date: August 31, 1965
Creator: Arnold, J. L.; Miller, K. J. & Peterson, R. M.
Partner: UNT Libraries Government Documents Department
open access

The High-Temperature Irradiation Behavior of Hypostoichiometric Uranium Monocarbide

Description: From abstract: A series of three multi-compartmented experiments was designed to investigate the irradiation behavior uranium carbide fuels, as a function of composition, temperature, and burn-up; and the mechanical properties of Type 304 stainless steel, as a function of temperature and integrated thermal neutron flux.
Date: August 31, 1965
Creator: Hahn, R. D.
Partner: UNT Libraries Government Documents Department
open access

Large SGR Control Rod Development

Description: From abstract: A development program was initiated to design, fabricate and test an absorber column with a 10 to 12 year lifetime, for use in the proposed LSGR.
Date: July 25, 1965
Creator: Dermer, M. D.
Partner: UNT Libraries Government Documents Department
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