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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
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
Rolling and Welding Type 430M Tubes to Stainless Steel Overlaid Carbon Steel Tubesheets
In the fabrication of the steam generator on APPR-1A it was considered necessary to roll the Type 430M tubes into carbon steel tube-sheets. The rolled joint was a necessary precaution to prevent secondary water from contacting the stainless steel weld.
Date:
February 16, 1959
Creator:
Bennett, R. W.; Meister, R. P. & Kerton, R. J.
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
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
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
Temperature Distribution and Thermal Stress in Reactor Core APPR-1
The study was conducted to determine the adequacy of the fuel element structural design of APPR-1. The results obtained lead to the conclusion that the element design is structurally sound for all normal operating conditions from the standpoint of thermal stress.
Date:
February 15, 1956
Creator:
Berggren, W. P. & Kroeger, H. R.
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
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
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
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
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
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
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
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
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
Shielding Calculations for APPR-1 Demineralizer Shipping Containers
Calculations have been performed to determine the thickness of lead shielding required for a shipping container for a demineralizer used with the APPR-1 reactor facility.
Date:
April 26, 1957
Creator:
DeYoung, R. C.
System:
The UNT Digital Library
Inspection of Dummy Fuel Loading Used During the Non-Critical Test Run
This memo covers the inspection of the dummy fuel loading before and after the non-critical test runs
Date:
June 3, 1957
Creator:
Edgar, E. C.
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
APPR-1 Axial Non-Uniform Burn-Up-Initial Studies
Calculations used in previous studies are being modified with the results reported in this study.
Date:
March 28, 1956
Creator:
Fairbanks, F. B.
System:
The UNT Digital Library
Matrix Inversion on IBM 650-Program 40
A computer program designed to solve matrix inversion equations on an IBM 650
Date:
March 22, 1956
Creator:
Fairbanks, F. B.
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