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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
open access

Calandria Core Weld Joint Development

Description: Abstract: The design and initial test of cutting and welding equipment developed to remotely cut and re-weld the bottom process tube joint are discussed in this report.
Date: June 30, 1965
Creator: Roberts, J. G.
Partner: UNT Libraries Government Documents Department
open access

Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 5: July-December 1964

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: June 15, 1965
Partner: UNT Libraries Government Documents Department
open access

Increasing Thermocouple Reliability for in-Pile Experiments

Description: Abstract: The results indicated that increased reliability can be obtained by using thermocouples made with insulation of increased density and/or a low thermal expansion sheath.
Date: April 20, 1965
Creator: Babbe, E. L.
Partner: UNT Libraries Government Documents Department
open access

Flux Control for Irradiation Experiments

Description: Abstract: This report reviews various means which have been used to control experimental conditions in irradiation experiments, and presents the concept of local flux control.
Date: February 1, 1965
Creator: McCarty, W. K.
Partner: UNT Libraries Government Documents Department
open access

Fatigue Characteristics of 37-Tube, Modular, Steam Generator Head

Description: Abstract: This report presents the pertinent results of a series of fatigue tests relating to the evaporator and superheater 37-tube module heads for the sodium heated steam generator described in NAA-SR-9826.
Date: February 20, 1965
Creator: Lemcoe, M. M.
Partner: UNT Libraries Government Documents Department
open access

SRE Heat Transfer System Demolition

Description: From introduction: This report details the extensive modifications to the SRE heat transfer systems required to accomplish increased capacity objectives.
Date: August 31, 1965
Creator: Nicholson, J. O.
Partner: UNT Libraries Government Documents Department
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