Technical Report Archive & Image Library (TRAIL) - 177 Matching Results

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The Alco Products Inc. Criticality Facility : Description and Operation

Description: 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.
Partner: UNT Libraries Government Documents Department
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Analysis of Extended Zero Power Experiments on the Army Package Power Reactor : ZPE-2

Description: Introduction: This report is principally concerned with analysis of measurements taken on the APPR-1 core during the course of the extended Zero Power Experiments (ZPE-2). The bulk of these measurements are reported in APAE No. 21. There are some additional measurements reported in APAE Memo 115. In addition to the analysis of the ZPE-2 data some re-evaluation has been made of a few of the results obtained from the first set of Zero Power Experiments (ZPE-1). The ZPE-1 measurements are repor… more
Date: May 7, 1958
Creator: Byrne, B. J. & Oby, P. V.
Partner: UNT Libraries Government Documents Department
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Analysis of Primary System Blowdown by Rupture Disc Failure

Description: 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: unknown
Creator: Johnson, Carl G.
Partner: UNT Libraries Government Documents Department
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Analysis of Zero Power Experiments on SM-1 Core II and SM-1A Core I

Description: Abstract: An analysis of SM-1 Core II and SM-1A Core I zero power experiments was made by comparing these cores to each other and to AM-1 Core I on the basis of critical bank positions, bank calibrations and available chemical analyses of the fuel plate compositions. The effects of replacing boron absorbers by europium absorbers upon rod worth and stuck rod conditions were studied. Comparisons of measured and calculated power distributions were made. It was concluded that both SM-1 Core II an… more
Date: October 5, 1960
Creator: Paluszkiewicz, S.
Partner: UNT Libraries Government Documents Department
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APPR-1 Axial Non-Uniform Burn-Up-Initial Studies

Description: Calculations used in previous studies are being modified with the results reported in this study.
Date: unknown
Creator: Fairbanks, F. B.
Partner: UNT Libraries Government Documents Department
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APPR-1 Burnout Calculations

Description: 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: unknown
Creator: Williamson, T. G.
Partner: UNT Libraries Government Documents Department
open access

APPR-1 Control Rod Experiments and Calulations

Description: The methods used to treat partially and fully inserted APPR-1 control rods are described
Date: unknown
Creator: Fairbanks, F. B. & Gallagher, J. G.
Partner: UNT Libraries Government Documents Department
open access

ATBAC Check Calculation on the IBM 650, Program No. 303

Description: 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: unknown
Creator: Beretsky, I. & Oby, P. V.
Partner: UNT Libraries Government Documents Department
open access

Bobcat (Program No. 56) Code Preparation Analysis on the IBM-650

Description: 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: unknown
Creator: Bobe, P. E. & Caton, R. L.
Partner: UNT Libraries Government Documents Department
open access

A Boiling Water Analysis Code on the IBM-650

Description: 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: unknown
Creator: Beretsky, I. & Pacine, S.
Partner: UNT Libraries Government Documents Department
open access

BWR Reference Design for PL-3

Description: Abstract: The natural circulation, direct cycle, boiling water reactor reference design presented in this technical report is the alternate to the preferred preliminary design developed under Phase I of the PL-3 contract. The report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant eq… more
Date: February 28, 1962
Creator: Humphries, G. E.
Partner: UNT Libraries Government Documents Department
open access

Calculation of Control Rod Worth in APPR-1

Description: 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: unknown
Creator: Giesler, H. W. & Gallagher, J. G.
Partner: UNT Libraries Government Documents Department
open access

Comparison of Boron and Hafnium in APPR Control Rods

Description: 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: unknown
Creator: Johnson, W. R.
Partner: UNT Libraries Government Documents Department
open access

Comparison of Gaseous Waste Handling Systems for PL-3

Description: This report compares gaseous waste handling systems for direct and indirect boiling water and pressurized water reactors for PL-3 application
Date: unknown
Creator: Noble, J. H. & Duke, E. E.
Partner: UNT Libraries Government Documents Department
open access

Control and Dynamics Performance of a Sodium Cooled Reactor Power System

Description: Introduction: Objectives and Method of Approach. High plant efficiencies can be realized without excessively high core temperatures and high coolant pressures by the use of liquid metal coolant. In an attempt to prove the feasibility of liquid sodium as a reactor coolant ALCO Products, Inc., under sponsorship of the Atomic Energy Commission, is undertaking a design study of three vital system components: the intermediate exchanger, the boiler, and the superheater. Since, in the past programs,… more
Date: 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
open access

Control Rod Drive Development

Description: 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: unknown
Creator: Tully, J. P.; Connolly, T. F. & Anderson, R. E.
Partner: UNT Libraries Government Documents Department
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