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Calandria Core Weld Joint Development
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.
System:
The UNT Digital Library
A Rotary Kiln for the Controlled Oxidation of UC
Abstract: A rotary kiln was evaluated for the controlled oxidations of UC.
Date:
June 30, 1965
Creator:
Strausberg, S.
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 5: July-December 1964
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
Creator:
unknown
System:
The UNT Digital Library
SNAP 10A FSEM-3 Agena Compatibility Test
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.
System:
The UNT Digital Library
Increasing Thermocouple Reliability for in-Pile Experiments
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.
System:
The UNT Digital Library
SRE Mark II Fuel Handling Machine
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.
System:
The UNT Digital Library
Development of High-Temperature Electrical Ground Test Heaters for the SNAP 10A Program
Introduction: The development and qualification of the system acceptance test heaters and the reactor simulator heater are described in this progress report.
Date:
March 1, 1965
Creator:
Blevitt, R.; Paine, G. & Sudar, S.
System:
The UNT Digital Library
Fatigue Characteristics of 37-Tube, Modular, Steam Generator Head
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.
System:
The UNT Digital Library
Application of Nuclear Power Plants (SNAP Units) to the Manned Orbiting Research Laboratory (MORL)
Abstract: This report describes in detail two designs of a nominal 6-kwe Nuclear Power Plant (NPP), one using thermoelectrics for power conversion and the other using the Mercury-Rankine cycle NPP.
Date:
February 1, 1965
Creator:
Botts, W. V.; Marko, M.; McCourt, P. E.; Keshishian, V.; Piccot, A. R. & Budney, G. S.
System:
The UNT Digital Library
Final Design of Sodium-Heated, Modular, Steam Generators for the SCTI
Abstract: The following report covers the final design of the modular steam generators.
Date:
February 1, 1965
Creator:
Casey, D. F.; Hammer, J. J.; Logan, D. & Williams, M. C.
System:
The UNT Digital Library
Flux Control for Irradiation Experiments
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.
System:
The UNT Digital Library
Irradiation Swelling, Phase Reversion, and Intergranular Cracking of U-10 wt % Mo Fuel Alloy
Abstract: A fuel development program has been conducted, to investigate the behavior of U-10 wt% Mo alloy at the fission rates and temperatures anticipated in Core I of the Hallam Nuclear Power Facility.
Date:
February 1, 1965
Creator:
Willard, R. M. & Schmitt, A. R.
System:
The UNT Digital Library
The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1
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.
System:
The UNT Digital Library
200-Mwe Prototype Large SGR: Reactor Structure Design and Evaluation
From abstract: This document presents the reactor structure design and evaluation for a 200-Mwe prototype large SGR.
Date:
1965
Creator:
North American Aviation. Atomics International Division.
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 4: January-June 1964
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:
December 15, 1964
Creator:
Cole, H. S.; Hausknecht, D. F.; Jenkins, O. G., Jr.; Lew, D. E.; Mandel, H.; Pearson, E. N. et al.
System:
The UNT Digital Library
Material Bucklings of Critical and Subcritical Uranium Carbide Fueled Graphite Assemblies: Part 1, Experiment
Introduction: A series of critical and subcritical experiments have been carried out as part of the Advanced Sodium Graphite Reactor (ASGR) Critical Experiments program to provide physics information which would be directly applicable to the AGSR concept.
Date:
December 1, 1964
Creator:
Hillig, O. R. & Latham, D. W.
System:
The UNT Digital Library
Refabrication and Encapsulation of Highly Irradiated Uranium Dioxide
Abstract: One hundred gram quantities of uranium dioxide, irradiated to burnup as great as 21,000 Mwd/MTU and previously reprocessed by AIROX (Atomics International Reduction Oxidation), were refabricated into high density pellets and encapsulated for re-irradiation.
Date:
December 1, 1964
Creator:
Guon, J.; Bodine, J. E. & Sullivan, R. J.
System:
The UNT Digital Library
Study of SCTI Control System
Introduction: This report has been prepared to document the extensive analytical work required to design the control system for the Sodium Components Test Installation (SCTI), constructed for the Atomic Energy Commission at the Atomics International field laboratory.
Date:
December 1, 1964
Creator:
Griffin, C. W.
System:
The UNT Digital Library
Analysis of Stresses in Bellows
Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date:
October 15, 1964
Creator:
Anderson, W. F.
System:
The UNT Digital Library
Boiling Studies for Sodium Reactor Safety: Part 2, Pool Boiling and Initial Force Convection Tests and Analyses
Abstract: In fulfillment of the general objective of developing information on two-phase flow required in the safety evaluation of sodium cooled reactors, pool and forced-convection boiling of sodium were studied both experimentally and analytically.
Date:
October 15, 1964
Creator:
Lurie, H. & Noyes, R. C.
System:
The UNT Digital Library
Design of an Experimental Bowable Fuel Element for the SRE
Abstract: An experimental bowable fuel element was developed to study temperature oscillations in the second core loading of the SRE.
Date:
October 15, 1964
Creator:
Peckinpaugh, C. L.
System:
The UNT Digital Library
Evaluation of Coolant Impurity Removal Equipment at the OMRE
Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date:
October 15, 1964
Creator:
Barbour, P. & Davis, W. W.
System:
The UNT Digital Library
Radiolysis Products of Polyphenyl Coolants: Part 3, Omre High Boilers
Abstract: The nature of the high boiling radiolysis products of OMRE coolants was studied extensively.
Date:
October 15, 1964
Creator:
Keen, R. T.; Orr, W. L.; Miller, L. J.; Sullivan, R. J. & Shepard, R. C.
System:
The UNT Digital Library
Sodium Reactor Experiment Power Expansion Program: Heat Transfer Systems Modifications
Abstract: Under the Power Expansion Program (PEP), modifications have been made to the Sodium Reactor Experiment (SRE) facility to improve plant reliability and permit an increase in power to 30 Mwt, with a reactor coolant outlet temperature up to 1200°F.
Date:
October 9, 1964
Creator:
Freede, W. J. & Roberts, J. K.
System:
The UNT Digital Library