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Pathfinder Atomic Power Plant Technical Progress Report: July 1, 1959-September 30, 1959
Foreword: This is the eighth of a series of reports covering technical progress on the research and development program being performed in connection with the design of the Pathfinder Atomic Power Plant.
Date:
February 1960
Creator:
unknown
System:
The UNT Digital Library
Symposium on High Flux Materials Testing Reactors: Held in Brussels, Belgium. September 21-26, 1959
From abstract: This paper discusses the use of high flux reactors to remove a number of deficiencies in the knowledge of the interaction of neutrons with matter.
Date:
June 1960
Creator:
unknown
System:
The UNT Digital Library
Nuclear Superheat Meeting: October 1960
From introduction: This report discusses AEC-sponsored nuclear superheat meetings whose primary purpose is to keep the AEC contractors engaged in nuclear superheat projects abreast of the overall AEC superheat program and to provide a means for the exchange of current technical information.
Date:
November 10, 1960
Creator:
Mravca, Andrew E.
System:
The UNT Digital Library
Advanced Pressurized Water Reactor Study [Part 1, Supplement]: Phase 2--A Report
From introduction: This report details the progress of the Advanced Pressurized Water Reactor Study.
Date:
February 1960
Creator:
Stone and Webster Engineering Corporation
System:
The UNT Digital Library
A Compendium of Information for Use in Controlling Radiation Emergencies: Including Lecture Notes from a Training Session at Idaho Falls, Idaho, February 12-14, 1958 (Revised)
From introduction: This report is a summary of the lecture material in the training course held at Idaho Falls, Idaho, to familiarize members of radiological assistance teams with information helpful in the response to an unusual accident including release of radioactive materials to a populated environment.
Date:
September 1960
Creator:
Brodsky, Allen & Beard, G. Victor
System:
The UNT Digital Library
Boiling Water Reactor Study [Part 1, Supplement]: Refinements of 306 Mw Power Reactor Conceptual Design
From introduction: The objectives of the study are to review the designs and costs of the 306 mw selected BWR and to determine the effect of refinements on plant performance and costs.
Date:
February 1960
Creator:
Ebasco Services Incorporated
System:
The UNT Digital Library
Boiling Water Reactor Study [Part 2, Supplement]: Separate Studies
From summary and conclusions: This study has been made to determine the feasibility of installing reheat steam facilities in conjunction with the selected 306-mw boiling water nuclear power plant.
Date:
February 1960
Creator:
Ebasco Services Incorporated
System:
The UNT Digital Library
Civilian Power Reactor Program, Part 3: Status Report on Heavy Water Moderated Reactors as of 1959
From discussion objective: The general purpose of all the programs reviewed in this report is to develop a reactor concept, utilizing natural fuel and heavy water moderator, that could lead to low-cost nuclear power.
Date:
1960
Creator:
U.S. Atomic Energy Commission
System:
The UNT Digital Library
Civilian Power Reactor Program, Part 3: Status Report on Sodium Graphite Reactors as of 1959
From summary: This report describes the current development status of the Sodium Graphite Reactor concept. The development history is summarized and all important areas of development are discussed.
Date:
1960
Creator:
U.S. Atomic Energy Commission
System:
The UNT Digital Library
Civilian Power Reactor Program, Part 3: Status Report on Fast Reactors as of 1959
From summary: The objective of the fast reactor program is to achieve economic power while burning a large fraction of the source uranium.
Date:
1960
Creator:
U.S. Atomic Energy Commission
System:
The UNT Digital Library
Civilian Power Reactor Program, Part 3: Status Report on Organic-Cooled Power Reactors as of 1959
From summary: This report presents a brief survey of the current status of technology on organic-cooled reactors.
Date:
1960
Creator:
U.S. Atomic Energy Commission
System:
The UNT Digital Library
Small Size Pressurized Water Reactor Conceptual Design: April 11, 1960
From foreword: The purpose of this conceptual design is to outline criteria for the selection and development of a reactor plant with a fossil fuel fired superheater, a conventional generator plant and auxilary systems constituting a complete operating unit capable of producing a gross electrical power output of 22,000 kw.
Date:
April 11, 1960
Creator:
unknown
System:
The UNT Digital Library
Thermal Cycling Tests of Porous Uranium
Abstract: It has been proposed that a fuel element containing porous uranium be used for moderately high temperature applications. In an effort to determine the structural integrity of this type of fuel body, thermal cycling tests have been conducted on porous uranium.
Date:
March 15, 1960
Creator:
Wilkinson, L. E.
System:
The UNT Digital Library
OMRE Fuel Removal and Shipping Equipment
Abstract: A portable assembly for handling and shipping OMRE fuel elements is described and details of its operation are given. Problems of heat transfer and radiation shielding are discussed, and detailed analysis are presented.
Date:
April 1, 1960
Creator:
Mallon, P. J.; Duncan, D. S. & Noyes, R. C.
System:
The UNT Digital Library
OMR (Piqua) Unitized Control-Safety Rod Prototype Tests
Abstract: A unitized magnetic jack driven control-safety rod has been developed for the 45.5 thermal megawatt organic moderated reactor (Piqua).
Date:
June 30, 1960
Creator:
Howell, J. D. & Weeks, C. C.
System:
The UNT Digital Library
High Temperature Corrosion of Some Metals and Ceramics in Fluorinating Atmospheres
Abstract: The results of this investigation leave little doubt that diffusion of the fluorinating gas along the grain boundaries of the nickel fluoride film to react at the metal-scale interface is the primary mechanism of attack upon pure nickel and its more promising alloys.
Date:
September 30, 1960
Creator:
Hale, C. F.; Barber, E. J.; Bernhardt, H. A. & Rapp, Karl E.
System:
The UNT Digital Library
Performance of HNPF Prototype Free-Surface Sodium Pump
Abstract: A free-surface centrifugal pump, incorporating a hydraulic bearing running in sodium, was operated at the conditions required for service in the HNPF.
Date:
1960
Creator:
Atz, R. W.
System:
The UNT Digital Library
Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service
Abstract: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of commercially available valves considered for use in the sodium coolant system of the Hallam Nuclear Power Facility.
Date:
May 1, 1960
Creator:
Baroczy, C. J.
System:
The UNT Digital Library
Safe Handling of Chlorine Trifluoride and the Chemistry of the Chlorine Oxides and Oxyfluorides
Abstract: A discussion of the potential hazards of chlorine trifluoride is presented and a series of safe handling procedures is recommended.
Date:
November 11, 1960
Creator:
Farrar, R. Lynn, Jr.
System:
The UNT Digital Library
300,000-KWE SGR Nuclear Power Plant of Current Technology
Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
Date:
August 1, 1960
Creator:
Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
System:
The UNT Digital Library
Reactor Technology Report Number 13: Engineering
Quarterly report issued by the Knolls Atomic Power Laboratory to report to the industry on developments in unclassified reactor technology. This issue focuses on engineering information.
Date:
June 1960
Creator:
unknown
System:
The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: February-April 1960
Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. It includes descriptions of progress and studies conducted during the report period, with tables, illustrations, and photographs.
Date:
August 9, 1960
Creator:
Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
System:
The UNT Digital Library
Automatic Recording Unit
From abstract: The PT-750 is designed to be used in conjunction with a production tester which requires automatic recording of test data. This manual provides a source of procedures and reference material necessary in automatic recording and in use of the PT-750.
Date:
March 29, 1960
Creator:
Ross, Frank A.
System:
The UNT Digital Library
Steady-State Tests of a Reactor Safety Device
Introduction: This is the fourth report in a series of reports dealing in particular with a reactor safety device of a double diaphragm type.
Date:
December 15, 1960
Creator:
Springer, T. H.
System:
The UNT Digital Library