Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution (open access)

Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution

Comparison of the economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO2 nuclear fuels.
Date: April 23, 1962
Creator: Adams, J. B.; Benis, A. M. & Watson, C. D.
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System

Final design for the 30 megawatt intermediate heat exchanger and steam generator.
Date: January 31, 1962
Creator: Alco Products (Firm)
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis

Chemical engineering analysis and stress analysis for design of the 3 megawatt intermediate heat exchanger and steam generator for service with a liquid sodium heat transfer fluid.
Date: February 28, 1962
Creator: Alco Products (Firm)
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
Control and Dynamics Performance of a Sodium Cooled Reactor Power System (open access)

Control and Dynamics Performance of a Sodium Cooled Reactor Power System

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, the nuclear reactor had been the major focus of attention, the development of the sodium cooled reactor and sodium pumps for this application are thought to need the less development than the heat exchanger equipment. Consequently, parallel design studies of the reactor, pumps, and other system components have not yet been initiated.
Date: 1960
Creator: Alco Products (Firm).
System: The UNT Digital Library
Evaluation of Kanigen, Electroless Nickel Plating for Steam Side of a Sodium Component Steam Generator (open access)

Evaluation of Kanigen, Electroless Nickel Plating for Steam Side of a Sodium Component Steam Generator

Introduction: This is a final report on the evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam i a sodium heated AISI Type 316 stainless steel steam generator. The purpose of the coasting was to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It has been concluded that the kanigen coating does not afford adequate protection for the services condition intended. This work was performed as part of the research and development program for the United States Atomic Energy Commission sodium Components Design Project.
Date: February 15, 1961
Creator: Alco Products (Firm).
System: The UNT Digital Library
Intermediate Heat Exchanger and Steam Generator Final Design. Volume 1. Thermal & Mechanical Design (open access)

Intermediate Heat Exchanger and Steam Generator Final Design. Volume 1. Thermal & Mechanical Design

This technical report represents the final design for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming fro the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to the steam generator. Because of radioactivity the unit will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shutdown it will be necessary to allow time for radioactive decay before the unit will be accessible to personnel. Because of inaccessibility and possible long periods allowed for decay time, it is imperative that the unit give trouble free operation. During periods of shutdown, the internals should have easy access for inspection and repair if necessary so that down time is held to a minimum. The steam generator is designed to generate superheated steam using liquid sodium from the intermediate heat exchanger as the heat source. Its basic design is a shell and tube unit made up of three difference sections: (1) a …
Date: September 30, 1960
Creator: Alco Products (Firm).
System: The UNT Digital Library
Intermediate Heat Exchanger and Steam Generator Final Design. Volume 2. Chemical & Stress Analysis (open access)

Intermediate Heat Exchanger and Steam Generator Final Design. Volume 2. Chemical & Stress Analysis

Introduction: This volume deals principally with the chemical analysis and the stress analysis for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The work presented is an extension and modification of the analysis presented in the preliminary design report. The chemical analysis covers the sodium cover gas system and the effects of sodium-water reactions in the event of a leak in the steam generator. Considerable design work was done in an effort to maintain the integrity of the steam generator vessel under maximum leak conditions. The method of sizing relief valves for each unit under varying leak rates is presented in this text and operation of the unit for the various leak rates is resented in the Operation and Maintenance volume. The stress analysis section covers those thermal transients which would be physically possible with this intermediate heat exchanger and steam generator design. Attention has been given to methods of operation which would minimize the magnitude and frequency of thermal shocks. Certain areas have been studied in detail where thermal stresses appear high. This report also includes a structural design basis for handling stress analysis of combined mechanical, hydrostatic and thermal stresses and conditions …
Date: September 30, 1960
Creator: Alco Products (Firm).
System: The UNT Digital Library
Intermediate Heat Exchanger and Steam Generator Final Design. Volume 3. Specifications (open access)

Intermediate Heat Exchanger and Steam Generator Final Design. Volume 3. Specifications

Introduction: Sodium Components Material Specifications. Twenty-three material, inspection and welding specification are presented for the various parts of both the intermediate heat exchanger and steam generator. Tables indicate the applicable parts and assemblies to which these specifications shall apply. For other parts, where the material requirements are not severe, the ASTM or other indicated specifications shall apply.
Date: September 30, 1960
Creator: Alco Products (Firm).
System: The UNT Digital Library
Intermediate Heat Exchanger and Steam Generator Final Design. Volume 4. Operation & Maintenance (open access)

Intermediate Heat Exchanger and Steam Generator Final Design. Volume 4. Operation & Maintenance

This technical report contains the operation and maintenance specifications for the intermediate heat exchanger and the steam generator. The report contains eight sections: (1) General Information, (2) Shipping and Installation, (3) Operation Procedures, (4) Scram and Casualty Shutdowns, (5) Leaks, (6) Instrumentation and Control, (7) Maintenance, and (8) four Appendixes (a) Boiler Water Chemistry Recommendations, (b) Final Concept Drawings, (c) Industrial Nucleonics Literature on Liquid Level Detector, and (d) Sodium Purity Control Recommendations.
Date: September 30, 1960
Creator: Alco Products (Firm).
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
Test Program for 30 Megawatt Prototype Sodium Intermediate Heat Exchanger and Steam Generator (open access)

Test Program for 30 Megawatt Prototype Sodium Intermediate Heat Exchanger and Steam Generator

The designer's concept of a test program for the 30-Mw prototype intermediate heat exchanger and steam generator designed and fabricated as part of the Sodium Components Development Program is presented. The performance data will serve to verify the thermal design, or allow application of improved techniques to future designs, give an improved basis for stress analysis in design of future units, and demonstrate the capability and limitations of the units in relation to the performance specifications for which they were designed. Welding techniques for type 316 stainless steel are described. The specifications and operating conditions of the units are given along with instrumentation drawings showing test equipment design and arrangement.
Date: September 14, 1962
Creator: Alco Products (Firm).
System: The UNT Digital Library
Tube-To-Tubesheet Welding Development Programs to 30 Megawatt Prototype Sodium Intermediate heat Exchanger and Steam Generator (open access)

Tube-To-Tubesheet Welding Development Programs to 30 Megawatt Prototype Sodium Intermediate heat Exchanger and Steam Generator

Special welding techniques for joining Inconel weld overlays on type 316 stainless steel tubesheets and channels are described. The program for the development of the required welding procedures are divided into three specific programs: overlaying Inconel filler Metal 82 on type 316 stainless steel, welding type 316 stainless steel tubes to a type 316 stainless steel tubesheet, and welding Inconel-type 316 stainless steel composite tubes to Inconel weld overlaid type 316 tubesheets. Shock tests are described which attempt to assimilate the most drastic thermal transient that could occur in both units and to evaluate the effect of the resulting stresses on the Inconel overlay and the tube-to-tubesheet welds. (N.W.R.)
Date: 1963
Creator: Alco Products (Firm).
System: The UNT Digital Library
X-Ray Fluorescence Tables: Program Description (open access)

X-Ray Fluorescence Tables: Program Description

Report discussing the mechanics of X-Ray and COMBO computer programs.
Date: July 20, 1964
Creator: Amsbury, W. P.; Lee, W. W.; Rowan, J. H. & Walden, G. E.
System: The UNT Digital Library
Plutonium Recycle Critical Facility: Final Safeguards Analysis (open access)

Plutonium Recycle Critical Facility: Final Safeguards Analysis

Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.
Date: February 1962
Creator: Anderson, J. K. & Winegardner, W. K.
System: The UNT Digital Library
Halogen Collector Test Program (open access)

Halogen Collector Test Program

Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date: March 1, 1960
Creator: Arthur D. Little, Inc.
System: The UNT Digital Library
Fast Flux Test Facility Studies Progress Report: April 1965 (open access)

Fast Flux Test Facility Studies Progress Report: April 1965

From abstract: "...limited study work was performed on the conceptual design of the proposed fast flux test facility and information was obtained in important areas of supporting technology."
Date: April 1965
Creator: Astley, E. R.
System: The UNT Digital Library
Enrico Fermi Atomic Power Plant (open access)

Enrico Fermi Atomic Power Plant

Report describing the Enrico Fermi Atomic Power Plant, its fast breeder reactor, and heat transport systems.
Date: March 1960
Creator: Atomic Power Development Associates
System: The UNT Digital Library
Fast Reactor Core Design Parameter Study (open access)

Fast Reactor Core Design Parameter Study

Report describing parametric studies of eleven fast reactor fuel systems undertaken to determine the design and economic factors for producing electricity. The methods used for making the parametric studies are described, as well as the results of these studies. Appendices begin on page 103.
Date: March 1960
Creator: Atomic Power Development Associates
System: The UNT Digital Library
Final Design Report: DR-1 Gas Loop (open access)

Final Design Report: DR-1 Gas Loop

Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
Date: March 1961
Creator: Baars, R. E.
System: The UNT Digital Library
Irradiation Performance of Thoria-Urania Fuel Materials: Quarterly Technical Report, Number 2, October - December 1964 (open access)

Irradiation Performance of Thoria-Urania Fuel Materials: Quarterly Technical Report, Number 2, October - December 1964

From introduction: "Complete exploitation of the advantages of thorium as a fertile material in thermal and particular resonant spectrum reactors has been inhibited by the lack of quantitative physical property data for thoria and thoria-urania fuels."
Date: October 1964
Creator: Babcock & Wilcox Company
System: The UNT Digital Library
Heavy-Water-Moderated Power Reactors: a Status Report (open access)

Heavy-Water-Moderated Power Reactors: a Status Report

From introduction: "Evaluation of the present economic and technological status of power reactors that are cooled and moderated by heavy water and fueled with natural uranium."
Date: March 1960
Creator: Babcock, Dale Friend
System: The UNT Digital Library
Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow (open access)

Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow

Two-phase flow-regime transitions at elevated pressures for a single-component, trichloromonofluoromethane, were investigated for forced-circulation, upward flow in a vertical, rectangular conduit with internal dimensions of 0.380 by 1.050 inches.
Date: September 1965
Creator: Baker, James L. L.
System: The UNT Digital Library
Evaluation of Failed Hot Gas Isostatic Pressed Fuel Rods (open access)

Evaluation of Failed Hot Gas Isostatic Pressed Fuel Rods

From introduction: "Evaluations to determine cause of fuel rods breakage following irradiation."
Date: March 20, 1963
Creator: Baroch, C. J. & Boyer, C. B.
System: The UNT Digital Library