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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
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
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
Thermal Analysis of APPR-1 at Midlife : Based on Actual Core Design
The purpose of the study is to determine the calculated margin between peak surface temperature and the maturation temperature corresponding to a pressure of 1200 psia.
Date:
January 2, 1956
Creator:
Johnson, Carl Gunnard, 1902-1966
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
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
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
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
Thermal Stresses in the Pressure Vessel of the APPR-1
The thermal stress in the vessel wall depends upon the temperature distribution in the vessel wall. This study will focus on how the temperature distribution was calculated.
Date:
May 1, 1956
Creator:
Kroeger, H. & Silks, T. M.
System:
The UNT Digital Library
Hot Channel Factors and Power Distribution for the APPR-1
The hot channel factors and power distribution for the APPR-1 has been reviewed in light of the most recent reactor analysis and metallurgical information. An estimate of the heat release (per unit area) in the absorber section is included so that surface temperature of the absorber section can be checked
Date:
May 7, 1956
Creator:
Gallagher, J. G.
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
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
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The purpose of this analysis is to determine the shielding requirements for irradiated APPR-1 fuel elements both in the fuel element storage pit and in transit to the reprocessing plant.
Date:
July 6, 1956
Creator:
Fairbanks, R. B. & Morse, D. C.
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
Time Behavior Analysis of the Photoneutron and Polonium=Beryllium Sources in the APPR-1
The time behavior of the strength of the Po-BE source to be used in the APPR-1 was investigated assuming that, besides the polonium decay, burnup of the polonium and beryllium is taking place
Date:
August 21, 1956
Creator:
Rosolowski, J. H.
System:
The UNT Digital Library
Thermal Analysis of APPR-1 Core-III
The axial variation of metal surface temperature, within the central control red fuel section, was calculated from the worst anticipated axial power flux distribution and the average coolant flow velocity through the core.
Date:
September 17, 1956
Creator:
Harvey, C H.
System:
The UNT Digital Library
Results and Analysis of the APPR-1 Zero Power Experiments : Part 1
This report contains the results of the initial experiments performed on the APPR-1 core at the Alco Critical Facility, an interpretation of the experimental measurements, and a plan of operation for the APPR-1.
Date:
November 7, 1956
Creator:
Giesler, H. W.
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
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
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
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
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
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