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Comparison of Predicted and Actual Control Rod Drop Time Following Scram of the APPR-1
A detailed analysis of hydraulic and mechanical forces affecting control rod drop time has been made to determine a mathematical expression for rod position in terms of elapsed time after initiation of a scram.
Date:
July 12, 1957
Creator:
Brondel, J. O.
System:
The UNT Digital Library
Additional Measurements on the Army Package Power Reactor Zero Power Experiments ZPE-1 and ZPE-2
During the course of the ZPE-2 experimental program additional measurements were performed such as the evaluation of various absorber section compositions and reactivity studies designed to facilitate analytical techniques
Date:
November 15, 1957
Creator:
Giesler, H. W.
System:
The UNT Digital Library
Integral Flux Suppressor for APPR-1, Core II
An internal flux suppressor will be used for the APPR-1 Core II rather than an external suppressors employed in Core I. The reference design of the integral flux suppressor for Core II is described
Date:
April 10, 1958
Creator:
Leibson, M. J.
System:
The UNT Digital Library
APPR-1 Burnout Calculations
A general non-uniform burnup program has been developed to determine the lifetime of the APPR-1. Calculations are used to determine performance using two one dimensional multiregion burnout calculations
Date:
April 10, 1958
Creator:
Williamson, T. G.
System:
The UNT Digital Library
APPR-1 Reactor Transient Analysis : Volume I, Basic Kinetic Model and Equations
A basic kinetic model of the primary system coolant loop is developed for the Army Package Power Reactor-1
Date:
April 25, 1958
Creator:
Brondel, J. O.
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
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
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
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
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
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
Nuclear Excursion Analysis on the IBM 650 (Early Code)
The Early program is based on the design to compute the peak power and total energy release which will occur in a reactor due to a step increase of reactivity.
Date:
February 26, 1959
Creator:
Stueck, Clifford J. & Reiback, Earl M.--1931-2006
System:
The UNT Digital Library
Nuclear Excursion Analysis on the IBM 650 (Early Code)
The Early program is based on a design to compute the peak power and total energy release which will occur in a reactor due to a step increase of reactivity.
Date:
February 26, 1959
Creator:
Reiback, Earl M.., 1931-2006 & Stueck, Clifford J.
System:
The UNT Digital Library
Formerly (APPR-1) Research and Development Program (Interim Report on) Core Measurements, Task No. VII
Physics experiments were performed on the SM-1 (formerly APPR-1) core to evaluate temperature and pressure coefficients, transient xenon, neutron source requirements, safety margin and core reactivity as a function of core life.
Date:
March 1, 1959
Creator:
MacKay, S. D.; Tubbs, D. C. & Bagley, R. O.
System:
The UNT Digital Library
SM-2 Vault Criticality
In order to determine the safety of the location of the experimental fuel plates two criticality criteria were applied.
Date:
February 27, 1959
Creator:
Fried, B. E.
System:
The UNT Digital Library
SM-1 (APPR-1) Research and Development Program Activity Buildup Program Task 1
This report presents the results of experimental work performed from February to November 1958 to determine the nature and extent of the buildup of radioactivity in the primary system of the SM-1 (APPR-1).
Date:
1959-03-001
Creator:
Brown, William S.; Bergen, C. Richard; Bergmann, Carl A.; Chupak, Julius; Grant, Louis G. & Ryan, Susanne
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
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
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
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-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
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 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