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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
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
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
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
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
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
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