Serial/Series Title
Country
69 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
69
next
The Alco Products Inc. Criticality Facility : Description and Operation
The Alco Products Criticality Facility, site location, and operating procedures are described in detail, including the handling of fissionable material and the operating procedures for the safe performance of critical experiments.
Date:
July 16, 1958
Creator:
Noaks, John W.
System:
The UNT Digital Library
SM-2 Task 3 Mechanical Design Report: October 1958 to March 1960
Progress on design studies under Task 3, the mechanical design portion of the SM-2 Core and Vessel design, is summarized for the period October 1958 to March 1960
Date:
September 20, 1960
Creator:
Connolly, T. F.
System:
The UNT Digital Library
Specifications and Fabrication Procedures for PM-2A Core II Neutron Absorber Sections
The specifications cover materials and process required to produce the absorber sections.
Date:
May 13, 1960
Creator:
Nuclear Power Engineering Department
System:
The UNT Digital Library
Specifications and Fabrication Procedures for PM02A Core II Control Rod Fuel Elements
Stainless steel-base fuel components of thin plate-type construction and containing a dispersion of UO2 have been successfully employed in powering the Army Package Power Reactor.
Date:
May 13, 1960
Creator:
Nuclear Power Engineering Department
System:
The UNT Digital Library
Specifications and Fabrication Procedures for PM-2A Core II Stationary Fuel Elements
Stainless steel-base fuel components of thin plate-type construction and containing a dispersion of UO2 have been successfully employed in powering the Army Package Power Reactor (SM-1). The component is designed for radioactive service in pressurized water and consists of eighteen composite fuel plates joined into an integral unit or assembly by brazing.
Date:
May 13, 1960
Creator:
Nuclear Power Engineering Department
System:
The UNT Digital Library
Specifications and Fabrication Procedures for SM-1A Core II Neutron ABsorber Sections
The specifications described cover materials and process required to produce the absorber sections.
Date:
May 13, 1960
Creator:
Nuclear Power Engineering Department
System:
The UNT Digital Library
Specifications and Fabrication Procedures for SM-1A Core II Stationary Fuel Elements
The specifications described were prepared to aid in the procurement of stationary fuel elements for Core II of SM-1A from an industrial fuel element manufacture
Date:
May 13, 1960
Creator:
Nuclear Power Engineering Department
System:
The UNT Digital Library
Specifications and Fabrication Procedures for SM-1A Core II Control Rod Fuel Elements
Stainless steel-base fuel components of thin plate-type construction and containing a dispersion of UO2 have been successfully employed in powering the Army Package Power Reactor. The component is designed for radioactive service in pressurized water. Specifications covering loading, materials, and processing are presented.
Date:
May 13, 1960
Creator:
Nuclear Power Engineering Department
System:
The UNT Digital Library
SM-1 Reactor Vessel Penetrated Gasket Design and Test Report
Mechanical compression tests were performed on gasket test specimens machined to the cross-sectional dimensions of a stainless steel ring type gasket to be installed in the SM-1 reactor pressure vessel.
Date:
June 10, 1960
Creator:
Gebhardt, F. G.
System:
The UNT Digital Library
SM-1 Research and Development Quarterly Report : October 1 to December 31, 1959
This report covers Research and Development conducted at the SM-1 which includes progress being made in plant water chemistry and health physics practices and progress on individual tasks and tests.
Date:
April 8, 1960
Creator:
Obrist, C. H.
System:
The UNT Digital Library
SM-2 Reactor Core and Vessel Review Report
This report contains a recapitulation of activity in the SM-2 Core and Vessel Program during the period December 15, 1959 to March 18, 1960.
Date:
March 30, 1960
Creator:
Hoover, H. L.
System:
The UNT Digital Library
SM-2 Clutch Testing
The criteria and methods for test evaluation of electro-magnetic clutch characteristics are discussed
Date:
March 23, 1960
Creator:
Hauenstein, G. C.
System:
The UNT Digital Library
SM-2 Reactor Core and Vessel Monthly Report
This report contains the significant progress made on the SM-2 core and vessel program
Date:
February 19, 1960
Creator:
Gallagher, J. G.
System:
The UNT Digital Library
A Corrosion Study of Welded Stainless Steel Fuel Elements
This report covers fuel element corrosion studies conducted from April,1959 through July,1960, designed to aid in selecting and evaluating SM-2 fuel element welding techniques
Date:
December 22, 1960
Creator:
Bergen, C. R.
System:
The UNT Digital Library
Thermal Stress Testing of SM-2 Fuel Elements : Interim Technical Report
To determine thermal stability of SM-2 plate type fuel elements, test specimens were subjected to reactor operating temperature differences.
Date:
unknown
Creator:
Christenson, J. A.
System:
The UNT Digital Library
SM-1 Research and Development Quarterly Report : July 1, 1959 to September 30, 1959
This report covers research and development conducted by the ALCO Products, Inc. The report includes progress made in plant water chemistry and health physics practices.
Date:
January 15, 1960
Creator:
Obrist, C. H.
System:
The UNT Digital Library
SM-2 Reactor Core and Vessel Review Report
This review report contains a summary of the progress made since the last Review Meeting (September 16, 1959).
Date:
December 24, 1959
Creator:
Gallagher, J. G.
System:
The UNT Digital Library
Evaluation of Low Impurity Core Material in the SM-2
The worth of reduced cobalt and tantalum impurity concentrations of AISI Type 347 stainless steel in the SM-2 core cladding and structural material is evaluated on the basis of material costs involved and accessibility for maintenance
Date:
August 14, 1959
Creator:
Pancer, Guyon P. & Zegger, John L.
System:
The UNT Digital Library
Core Characteristics of Four Army Package Power Reactors
A brief discussion of the core characteristics of four uranium fuel, pressurized-water type Army Package Power Reactors is presented
Date:
June 15, 1959
Creator:
Gallagher, J. G.; Leibson, M. J. & Byrne, B. J.
System:
The UNT Digital Library
Interim Report No. 2 on Core Measurements : Task No. VII
Physics experiments were performed on the SM-1 core which included measurements made on five rod bank positions, rod calibrations, along with the reactivity effects of core modifications.
Date:
June 30, 1959
Creator:
MacKay, S. D. & Tubbs, D. C.
System:
The UNT Digital Library
Feasibility of Partial Chemical Control for the SM-2
Chemical control of the SM-2 was evaluated both as a partial substitute for burnable poison in the fuel element meat and as a means of improving plant performance.
Date:
May 15, 1959
Creator:
Gallagher, J. G.
System:
The UNT Digital Library
Reflector & Pressure Vessel Cooling & Thermal Stress Analysis on the IBM 650
The IBM programs are intended to assist in establishing reflector cooling requirements, as well as thermal stresses in the reflectors and pressure vessel.
Date:
March 26, 1959
Creator:
Love, J. D. & Caton, R. L.
System:
The UNT Digital Library
ATBAC Check Calculation on the IBM 650, Program No. 303
This program using the IBM 650 electronic data processing machine is used primarily as a tool in order to prepare input data for the IBM 704 code, entitle ATBAC. The code calculates steady state thermal characteristics of a plate type fuel element for both a nominal and adverse channel
Date:
March 13, 1959
Creator:
Beretsky, I. & Oby, P. V.
System:
The UNT Digital Library
A Boiling Water Analysis Code on the IBM-650
A method has been developed for using the IBM 650 Electronic Data Processing Machine to obtain detailed information concerning thermal and hydraulic conditions within a plate type reactor channel when the coolant in the channel is present in both vapor and liquid phases
Date:
March 10, 1959
Creator:
Beretsky, I. & Pacine, S.
System:
The UNT Digital Library