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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
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
Analysis of Primary System Blowdown by Rupture Disc Failure
The purpose of this study is to determine the time required for blowdown of the primary system when the rupture disc fails, and the effect of blowdown on the control rods during scram.
Date:
January 27, 1956
Creator:
Johnson, Carl G.
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
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 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
APPR-1 Low Power Test Program at the ALCO Critical Facility
Developing a test program to review reaching criticality with the minimum number of fuel elements
Date:
June 7, 1956
Creator:
Johnson, W. R.
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
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
Burnout Distribution in SM-1 (APPR-1) Control Rod Elements, Fixed Element #57 and adsorber sections at 10.5 MWYRS
An analytical prediction of the burnout distributions in particular SM-1 fuel elements and absorber sections after 10.5 MWYR of core energy release is given
Date:
June 5, 1959
Creator:
McElligott, P. E.
System:
The UNT Digital Library
Calculation of Control Rod Worth in APPR-1
7 rods were used in the APPR-1 rather than 5. The critical experiments and calculations from the use of the rods, including the capability of any four to shut down the cold reactor are examined in this study.
Date:
December 23, 1955
Creator:
Giesler, H. W. & Gallagher, J. G.
System:
The UNT Digital Library
Comparison of Boron and Hafnium in APPR Control Rods
There is a possibility of dimensional instability in the B-10-iron APPR-1 control rods due to helium production. This effect will be evaluated in this study.
Date:
April 26, 1956
Creator:
Johnson, W. R.
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
Control Rod Drive Development
This study was conducted to determine the operating and performance characteristics of the ORNL concept of control rod drive mechanism as applied to APPR-1
Date:
August 15, 1957
Creator:
Tully, J. P.; Connolly, T. F. & Anderson, R. E.
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
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
Critical Mass Calculation for AOOR-1 Critical Experiment
In order to check previous calculations, and to provide a tool for future analytical work on APPR type reactors, a calculation to predict the critical mass of the APPR critical experiment has been performed
Date:
February 23, 1957
Creator:
Gallagher, J. G.; Giesler, H. W. & Johnson, W. R.
System:
The UNT Digital Library
Current Status of APPR-1 Fuel Element Metallurgy
Provides update of fuel elements developed by ORNL for the APPR-1 reactor
Date:
July 23, 1956
Creator:
Robertson, R. D.
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
Emergency Shutdown of the APPR-1 by Poisoning with Boron
As described in this report, the APPR-1 will be operated with Rods A and B full out and with the other five rods ganged.
Date:
November 26, 1956
Creator:
Meem, J. L. & Knighton, G. W.
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
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