High-Level Radioactive Waste Management Alternatives Section 1: Summary, Section 2: Background and Data Base, Section 3: Evaluation Methodology (open access)

High-Level Radioactive Waste Management Alternatives Section 1: Summary, Section 2: Background and Data Base, Section 3: Evaluation Methodology

From foreword: "This report is a comprehensive overview study of potential alternative methods for long-term management of high-level radioactive waste."
Date: May 1974
Creator: Schneider, K. J. & Platt, A. M.
System: The UNT Digital Library
A Computer Program for Determining First-Collision Neutron Doses (open access)

A Computer Program for Determining First-Collision Neutron Doses

Data processing program written to compute the neutron dose received by individuals exposed in a nuclear excursion.
Date: May 21, 1962
Creator: McMurray, C. S.
System: The UNT Digital Library
Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959. (open access)

Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959.

Abstract: This technical report contains a description of the nuclear analysis performed upon the SM-2 core and vessel for the period September 1, 1958 to December 31, 1959. Calculations are given for core reactivity, power distributions, lifetime, reactor control, kinetics, radiation problems, fuel and poison burn-ups, and the nuclear effects of poisons, temperature, and geometry. Wherever possible, experimental data is included in order to test the validity of the analytical models. The SM-2 nuclear analysis was performed by Alco Products, in. under Tasks 1, 8, and 10 of Contract No. AT(30-2)-326 for the Atomic Energy Commission.
Date: May 27, 1960
Creator: Bobe, P. E.; Birken, S. H.; Byrne, B. J.; Clancy, E. F. & Fried, B. E.
System: The UNT Digital Library
Scale "Up or Down" Analysis for Prototype Test (open access)

Scale "Up or Down" Analysis for Prototype Test

Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually tested. In addition, these considerations include aspects required to accurately predict the performance, operation, mechanical reliability, and feasibility of fabrication of the 70 MW design.
Date: May 1, 1960
Creator: Alco Products (Firm).
System: The UNT Digital Library
Army PWR Support and Development Program Six Months Summary Report : October 1, 1961 - March 31, 1962 (open access)

Army PWR Support and Development Program Six Months Summary Report : October 1, 1961 - March 31, 1962

Abstract: Progress is reported on research and development tasks under the Program Plan for Engineering Support and Development of Army Pressurized Water Reactor Power Plants, Contract AT(30-1)-2639, during the six months' period October 1, 1061 to March 31, 1962.
Date: May 25, 1962
Creator: Dixon, M. H.
System: The UNT Digital Library
Analysis of Extended Zero Power Experiments on the Army Package Power Reactor : ZPE-2 (open access)

Analysis of Extended Zero Power Experiments on the Army Package Power Reactor : ZPE-2

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 reported in APAE No. 8. During the course of analysis work it became apparent that a considerable amount of basic experimental data had been taken on the APPR-1 core. It seemed worthwhile to organize this report in such a fashion that other investigators could make maximum use of this data. It provides excellent opportunity for individuals and groups interested in basic reactor reactor analysis problems to check calculational techniques. An attempt has been made to include all of the fundamental information concerning the material content and geometry of the APPR-1. This material is in included in the Appendices. In addition, cross-section files and group constants have been listed rather extensively in order that other investigators could compare results presented in …
Date: May 7, 1958
Creator: Byrne, B. J. & Oby, P. V.
System: The UNT Digital Library
Hazards Summary Report for the Army Package Power Reactor : SM-1, Task XVII (open access)

Hazards Summary Report for the Army Package Power Reactor : SM-1, Task XVII

Preface. This technical report is an updated and revised version of the original SM-1 (APPR-1) Hazards Summary Report. The original report was issued July 1955, almost two years before construction of the SM-1 plant was completed. During that time interval there were numerous design changes. Consequently, the original report does not accurately describe the plant as built. This revision is written after the SM-1 has been operated 3 years. It describes the as-build plant and includes plant modifications and experience obtained during the first 3 years of SM-1 operation.
Date: May 1960
Creator: Rosen, S. S.
System: The UNT Digital Library
Shielding Requirements for the Army Package Power Reactor (open access)

Shielding Requirements for the Army Package Power Reactor

Abstract. The design, selection, and calculation of the Army Package Power Reactor shielding are described. The APPR-1, a prototype of a package reactor for remote locations, has a primary shield of iron and water. this shield has been adopted to permit fast erection and to provide low transported weight. economically, including transportation cost, the iron water shield is better than a lead water shield and is competitive with a concrete shield for a remote site. Because of the location at Fort Belvoir,Va., the shielding requirements for the APR-1 are considerably more stringent than those for a reactor at a remote base. Since the secondary shielding which surrounds the entire primary system must provide protection for personnel at any location outside the vapor container, concrete is provided for this need.
Date: May 1, 1956
Creator: Meem, J. L. (James Lawrence). & Fairbanks, F. B.
System: The UNT Digital Library
Reactor Analysis for the Army Package Power Reactor No. 1 (open access)

Reactor Analysis for the Army Package Power Reactor No. 1

Abstract: The reactor analysis of the critical experiment and the APPR-1 resulted in a loading of the APPR-1 of 31.096 gm of B-10 with 22.5 kg U-335. This loading will result in adequate reactivity for a core life of 13 MWYR based on uniform burnup of U-335 and B-10. Calculations indicate that five of the seven control rods provided are more than adequate to shut the reactor down at any time. The temperature coefficient of reactivity should be at least -2 x 10-4 [delta] K/0F.
Date: May 29, 1956
Creator: Gallagher, J. G.; Giesler, H. W.; Johnson, W. R.; Fairbanks, F. B.; Oby, P. V. & Crouch, A. N.
System: The UNT Digital Library
Reactor Analysis for the Army Package Power Reactor No. 1 (open access)

Reactor Analysis for the Army Package Power Reactor No. 1

Abstract: The reactor analysis of the critical experiment and the APPR-1 resulted in a loading of the APPR-1 of 31.096 gm of B-10 with 22.5 kg U-335. This loading will result in adequate reactivity for a core life of 13 MWYR based on uniform burnup of U-335 and B-10. Calculations indicate that five of the seven control rods provided are more than adequate to shut the reactor down at any time. The temperature coefficient of reactivity should be at least -2 x 10-4 [delta] K/0F.
Date: May 29, 1956
Creator: Gallagher, J. G.; Giesler, H. W.; Johnson, W. R.; Fairbanks, F. B.; Oby, P. V. & Crouch, A. N.
System: The UNT Digital Library
The ML-1 Design Report (open access)

The ML-1 Design Report

From abstract: "This report describes the design of the mobile nuclear power plant which is to be the prototype of a mobile, low-powered nuclear power plant intended to furnish electrical power in remote locations."
Date: May 16, 1960
Creator: Linenberger, G. A.
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures

Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
Date: May 15, 1962
Creator: Alco Products (Firm)
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment: Operation and Testing of a Nonnuclear Liquid-Metal System (open access)

Liquid Metal Fuel Reactor Experiment: Operation and Testing of a Nonnuclear Liquid-Metal System

Extensive experimental program undertaken to provide data on the operation and testing of a bismuth-to-bismuth dual-loop system.
Date: May 1960
Creator: unknown
System: The UNT Digital Library
Heat Transfer Coefficients with Annular Flow During "One-Through" Boiling Water to 100 Per Cent Quality at 800, 1100, 1400 PSI (open access)

Heat Transfer Coefficients with Annular Flow During "One-Through" Boiling Water to 100 Per Cent Quality at 800, 1100, 1400 PSI

From introduction: "Once-Through boiling of water to 100 per cent steam quality was successfully accomplished. Results of Departure from Nucleate Boiling, transition, and film boiling tests are presented."
Date: May 1, 1961
Creator: Polomik, E. E.; Levy, S. & Sawochka, S. G.
System: The UNT Digital Library
Survey of Piping Failures for the Reactor Primary Coolant Pipe Rupture Study (open access)

Survey of Piping Failures for the Reactor Primary Coolant Pipe Rupture Study

From summary: "An industrial piping failure survey covering 701 contacts in electric utilities, petroleum refineries, chemical processing, marine applications, architect-engineers, component manufacturers, piping fabricating and erectors, insurance companies, and others was conducted as part of the Reactor Primary Coolant Rupture Study."
Date: May 1964
Creator: U.S. Atomic Energy Commission
System: The UNT Digital Library
Effect of Superheat and Moisture Separation on the SM-2 Design (open access)

Effect of Superheat and Moisture Separation on the SM-2 Design

From abstract: "The study evaluates the utilization of superheat and moisture separation techniques in the SM-2 design to improve the steam plant reliability and thermal efficiency. Ease of packaging, steam plant transient response, and capital costs are also considered. The reference design used for comparison is the steam cycle employing saturated steam at 600 psia described in APAE No. 40, Volume II."
Date: May 27, 1960
Creator: Phelps, E. F.
System: The UNT Digital Library
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 5, Fuel Element Rupture Testing Facility Analysis (open access)

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 5, Fuel Element Rupture Testing Facility Analysis

This report describes the final design of the Fuel Element Rupture Testing Facility and summarizes the safeguards analyses of the design and plans for operation.
Date: May 1963
Creator: Hanthorn, H. E.
System: The UNT Digital Library
Radium and Mesothorium Poisoning and Dosimetry and Instrumentation Techniques in Applied Radioactivity (open access)

Radium and Mesothorium Poisoning and Dosimetry and Instrumentation Techniques in Applied Radioactivity

A study on radium and mesothorium poisoning and dosimetry and instrumentation techniques in applied radioactivity.
Date: May 1958
Creator: Evans, Robley D.
System: The UNT Digital Library
Reactor Steam Power Plants: Economics (open access)

Reactor Steam Power Plants: Economics

Economic study covering several classes of cycles of reactor steam power plants.
Date: May 25, 1954
Creator: unknown
System: The UNT Digital Library
Operation of the 184" Cyclotron (open access)

Operation of the 184" Cyclotron

The operation of the 184" synchro-cyclotron is reviewed in terms of the theory as developed by the authors. Certain relevant data on the properties of the magnet and rotating condenser are also presented.
Date: May 17, 1949
Creator: Henrich, L. R.; Sewell, D. C. & Vale, J.
System: The UNT Digital Library
High Voltage Pulse Transformer Designs at University of California Radiation Laboratory (open access)

High Voltage Pulse Transformer Designs at University of California Radiation Laboratory

A report on high voltage pulse transformer designs at the University of California Radiation Laboratory.
Date: May 20, 1949
Creator: Baker, W. R.; Edwards, R. F.; Kerns, Q. A. & Reidel, J.
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment, Quarterly Technical Report: May 1957 - September 1957 (open access)

Liquid Metal Fuel Reactor Experiment, Quarterly Technical Report: May 1957 - September 1957

Quarterly technical report discussing progress and activities of the Liquid Metal Fuel Reactor Experiment.
Date: May 1957
Creator: Babcock & Wilcox Company
System: The UNT Digital Library
Design and Installation of a High Precision Temperature and Intimate Contact Monitor for Experimental Vacuum Chucks (open access)

Design and Installation of a High Precision Temperature and Intimate Contact Monitor for Experimental Vacuum Chucks

Describes the design criteria, design details, and final installation of a high precision temperature and intimate contact monitor.
Date: May 15, 1958
Creator: Morrow, G. W.
System: The UNT Digital Library
Description of Purex Plant Process (open access)

Description of Purex Plant Process

Description of Purex plant process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
Date: May 19, 1959
Creator: Irish, E. R.
System: The UNT Digital Library