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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-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
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
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 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 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 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
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
Vibration and Collapse Testing of SM-2 Fuel Elements : January 1959 to January 1960
Experiments were conducted on SM-2 fuel elements to ascertain if flow-induced fuel plate vibrations are an inherent operating characteristic.
Date:
July 5, 1960
Creator:
Morehouse, D. J. & Christenson, J. A.
System:
The UNT Digital Library
SM-2 Single Element Final Test Report
This report gives results of single element low pressure flow testing conducted on an SM-2 control rod assembly and stationary fuel element
Date:
October 28, 1960
Creator:
Krause, P. S.
System:
The UNT Digital Library
Health Physics Manual for the Army Package Power Reactor
The primary purpose of this manual is to adopt a radiological safety program to provide all personnel with a safe place in which to work, visit or live.
Date:
January 18, 1957
Creator:
Ball, B. M.
System:
The UNT Digital Library
Neutron Flux Suppression in APPR Control Rods
The detection of flux peaking in the APPR control rods in the water region immediately above the fuel elements resulted in an investigation into the effects of this peak.
Date:
January 10, 1957
Creator:
Johnson, W. R. & Oby, P. V.
System:
The UNT Digital Library
Two-Group Multiregion Axial Window Shade Calculation on the IBM 650
The code is a nine-region, two group finite difference calculation in slab geometry for the basic IBM 650 with a 2000 word storage capacity and one Type 533 unit. The code solves the steady-state two-group equation with fast and thermal fission.
Date:
March 29, 1957
Creator:
Fairbanks, F. B.
System:
The UNT Digital Library
APPR-1 Control Rod Experiments and Calulations
The methods used to treat partially and fully inserted APPR-1 control rods are described
Date:
March 6, 1957
Creator:
Fairbanks, F. B. & Gallagher, J. G.
System:
The UNT Digital Library
APPR-1 Hot Channel Factors: Re-Evaluation on the Basis of Manufacturing Experience and Zero Power Experiments
On the basis of recent experiment with APPR-1 fuel elements manufactured by ORNL,hot channel factors have been derived from the observed dimensional deviations
Date:
May 6, 1957
Creator:
Brondel, J. O.
System:
The UNT Digital Library
Effect of APPR-1 Control Rod Acceleration after Scram on Startup Accident
In the operation of the APPR-1 the most dangerous condition exists at cold startup. Therefore the behavior of the APPR-1 in a startup accident with a rod acceleration of 0.4 g after scram is considered
Date:
April 23, 1957
Creator:
Gallagher, J. G. & Silks, T. M.
System:
The UNT Digital Library
Shock Hydrodynamics of an Exploding Steam Pressure Vessel : Final Report
Initially issued as a brief survey of the shock problems associated with an assumed failure of a pressurizer vessel in a vapor container, this paper contains more detailed calculations and considerations of the analysis present in the original study.
Date:
November 25, 1955
Creator:
Porzel, F. B.
System:
The UNT Digital Library
The Preliminary Shield Design for the 50 MW Commercial Reactor
The investigation in this report were conducted to determine the required shielding to reduce radiation to a workable level, to determine the heeating in the various core components so coolant flow rates could be determined, and to determine the thermal stress and temperature distribution in the structural and load bearing members.
Date:
December 18, 1958
Creator:
Bagley, R. O., Jr.
System:
The UNT Digital Library
Primary Shielding Calculations on the IBM 650 (ROC Codes)
In order to calculate the gamma dose rates in the primary shielding of thermal reactors, four programs were written for thew IBM 650 computer.
Date:
October 15, 1958
Creator:
Rosen, S. S.; Oby, P. V. & Caton, R. L.
System:
The UNT Digital Library
Thermal Design Criteria for APPR Pressurized Water Reactors
The following criteria have been established for thermal design of APPR pressurized-water reactors in this study
Date:
November 26, 1958
Creator:
Love, J.
System:
The UNT Digital Library
Material Specifications for APPR-1 Core II Control Rod Fuel Elements and Absorber Sections
The specifications reported in this study are based on the results of development performed at Oak Ridge National Laboratory under the supervision of the Metallurgy Division.
Date:
December 30, 1958
Creator:
Edgar, E. C. & Robertson, R. D.
System:
The UNT Digital Library
Lovely-1, Program No. 55, Thermal Analysis on the IBM 650
This program is intended to be utilized for the establishment of flow requirements of a tailored flow core.
Date:
November 26, 1958
Creator:
Love, J. D. & Stueck, C. J.
System:
The UNT Digital Library
IBM 650 Computer, Program Number 755, Collation of ROC Code Output
Using the output of programs 653 and 654, each card of which contains the dose information for one dose point at one energy, program 655 produces the sum of the dose values of all energies for one dose point
Date:
December 19, 1958
Creator:
Stueck, C. J.
System:
The UNT Digital Library