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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
Economic Analysis of Replacement Cores for the SM and PM Type Reactors
An economic analysis is presented for the fabrication of replacement cores for SM and PM type reactors, including analysis of various core types and core fabrication technologies
Date:
October 5, 1961
Creator:
Wilder, A. S.
System:
The UNT Digital Library
Determination of Maximum Permissible Irradiation on Type 3 (SM-2) Fuel Plates
Two methods were used for predicting the maximum permissible burnup in Type 3 (SM-2) fuel plates: use of analytical models and use of existing irradiation data on U02 stainless steel dispersion fuel plates.
Date:
March 17, 1962
Creator:
Wilder, A. S. & Kelleman, R. W.
System:
The UNT Digital Library
Summary Nuclear Calculations for the SM-2 Core I
This report presents the results of a limited analysis of the Extended SM-2 Critical Experiments. A review of the analytical models is presented to ascertain the accuracy of the reactivity calculations for the reference SM-2 Core I
Date:
September 25, 1961
Creator:
Fried, B. E.; Beam, R. H. & Bobe, P. E.
System:
The UNT Digital Library
Interim Report on the Use of SM-2 Elements in SM-1, SM-1A and PM-2A Cores
Interim results of an analytical investigation of nuclear and thermal characteristics of SM-2 type fuel elements in SM-1, SM-1A and PM-2A reactor cores are reported
Date:
June 20, 1961
Creator:
Davidson, S. L. & Oggerino, J. P.
System:
The UNT Digital Library
Task XII Analytical Report SM-1 Transient Analysis by Analog Computer Methods
The voltage and frequency response of selected SM-1 plant system parameters to step load changes was analyzed using analog computer measurements.
Date:
May 26, 1961
Creator:
Barrett, J. A.
System:
The UNT Digital Library
Bobcat (Program No. 56) Code Preparation Analysis on the IBM-650
This report contains a description of the BOBCAT code, (Program 56), programmed for the IBM-650. The code greatly facilitates the nuclear analysis of APPR-type cores by performing many of the routine calculations necessary to obtain input to various IBM-650 and IBM-704 codes.
Date:
August 9, 1961
Creator:
Bobe, P. E. & Caton, R. L.
System:
The UNT Digital Library
Dynamic Simulation of Multi-Pass Pressurized Water Nuclear Power Plants by Analog Computer Techniques
A kinetic model of the primary loop of a muti-pass pressurized water reactor power plant is developed to evaluate, by analog computer techniques, the transient response characteristics due to steam generator load and reactor control rod perturbations.
Date:
June 1961
Creator:
Brondel, J. O.
System:
The UNT Digital Library
Flux and Power Distributions for the SM-2 Reference and Critical Experiment Cores
This report contains a detailed analysis of the power distribution in the SM-2 experimental core at 68°F and the SM reference core at 510°F
Date:
June 30, 1961
Creator:
Fired, B. E.; Alford, M. R. & Oggerino, J. P.
System:
The UNT Digital Library
Preliminary Stress and Fatigue Analysis of the SM-1 Primary System
A preliminary analysis of the SM-1 primary system showed it was safe from strain cycling damage with possible exception of steam generator tube sheet and primary pump casing
Date:
March 31, 1962
Creator:
Chittum, R. A.; Knipe, R. K. & McLaughlin, D. W.
System:
The UNT Digital Library
PWR Research and Development Program Test Report: Gamma Scanning Spent SM-1 Core I Fuel Elements Test 318
The test was designed and performed to experimentally determine fuel burnup distribution in the SM-1 Core I spent fuel elements
Date:
April 6, 1961
Creator:
Kemp, S. N.; McCool, W. J. & Moote, F. G.
System:
The UNT Digital Library
Activity Build-Up Control by High pH Coolant : A Literature Survey
A survey was made of unclassified literature dealing with the control of activity buildup in pressurized water reactors by high pH coolants
Date:
January 23, 1961
Creator:
Bergen, C. R.
System:
The UNT Digital Library
Nuclear Analysis of Various Spert-III Critical Experiments
The calculational models employed in the nuclear analysis of the SM-2 were applied to various critical experiments performed upon the SPERT-III core
Date:
April 27, 1961
Creator:
Paluszkiewica, S.
System:
The UNT Digital Library
SM-1 Research and Development Quarterly Report : April 1 to June 30, 1960
This report covers research conducted at the SM-1 and highlights progress made in plant water chemistry and health physics practices and progress on individual tasks and test are reported
Date:
September 20, 1960
Creator:
Bergman, C. A.
System:
The UNT Digital Library
Structural Testing of SM-2 Fuel Elements
Ability of the originally designed SM-2 stainless steel fuel elements, of both tungsten inert gas (TIG) and electrical resistance welded construction, to withstand static transverse pressure gradients of normal reactor operation was investigated
Date:
September 29, 1960
Creator:
Coleman, F. G., Jr. & Herbert, R. J.
System:
The UNT Digital Library
Summary of Reactor Design Information from Three Years Operation of a Small PWR
Reactor design information obtained from three years' operation of a small pressurized water reactor, the SM-1 (formerly APPR-1), presented and discussed
Date:
September 9, 1960
Creator:
Gallagher, J. G.
System:
The UNT Digital Library
Thermal Stress Testing of SM-2 Fuel Elements : Final Report January 1, 1959 to July 1, 1960
Thermal stress testing was performed on portions of reactor fuel elements.
Date:
September 20, 1960
Creator:
Christenson, J. A. & Kortheuer, J. D.
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
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 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