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Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design

Description: Preface: 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 from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary … more
Date: February 28, 1959
Creator: Alco Products (Firm)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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).
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Kanigen, Electroless Nickel Plating for Steam Side of a Sodium Component Steam Generator

Description: 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 r… more
Date: February 15, 1961
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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 encl… more
Date: September 30, 1960
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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 mainta… more
Date: September 30, 1960
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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).
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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… more
Date: September 30, 1960
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Scale "Up or Down" Analysis for Prototype Test

Description: 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 … more
Date: May 1, 1960
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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 specifica… more
Date: September 14, 1962
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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… more
Date: 1963
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Preliminary Shield Design for the 50 MW Commercial Reactor

Description: The investigation in this report were conducted to determine the required shielding to reduce radiation to a workable level, to determine the heeating in the various core components so coolant flow rates could be determined, and to determine the thermal stress and temperature distribution in the structural and load bearing members.
Date: unknown
Creator: Bagley, R. O., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Rolling and Welding Type 430M Tubes to Stainless Steel Overlaid Carbon Steel Tubesheets

Description: In the fabrication of the steam generator on APPR-1A it was considered necessary to roll the Type 430M tubes into carbon steel tube-sheets. The rolled joint was a necessary precaution to prevent secondary water from contacting the stainless steel weld.
Date: unknown
Creator: Bennett, R. W.; Meister, R. P. & Kerton, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Temperature Distribution and Thermal Stress in Reactor Core APPR-1

Description: 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: unknown
Creator: Berggren, W. P. & Kroeger, H. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SM-1 Research and Development Program: Long-lived Induced Activity Buildup During SM-1 Core I Lifetime. Task XVIII, Phase I

Description: Abstract: The results of activity buildup studies in the SM-1 performed during Core I lifetime (June 3, 1957 to April 28, 1960) are reported. Data are presented on the extent, nature, and mechanism of the buildup of long-lived gamma emitting nuclides in the reactor primary system. Radiation levels after reactor shutdown are presented, as well as mathematical equations used to account for the observed activity levels. The data have shown that Co60 is the major contributor to radiation levels in… more
Date: November 30, 1960
Creator: Bergmann, C. A.; Bergen, C.; Cox, J. F.; Chupak, J. & Grant, L. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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-… more
Date: May 27, 1960
Creator: Bobe, P. E.; Birken, S. H.; Byrne, B. J.; Clancy, E. F. & Fried, B. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Investigation of Local Boiling of SM-1

Description: Abstract; SM-1 Reactor Core I Rearranged and Spiked, and Core II with Special Components were analyzed under various off-design conditions to induce nucleate boiling. The steady state code, STDY-3, written for the thermal analysis of pressurized water cores, was employed for the analysis. The code performs a complete steady state parallel channel thermal analysis for both nominal and hot channels. Thermal characteristics of individual elements were investigated while changing the parameters of… more
Date: June 20, 1961
Creator: Bradley, P. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures.

Description: Abstract: Test procedures for special tests involving in-core SM-1 temperature and flow instrumentation are described (Task XIV Package Tests). These tests involve in-core steady state flow and temperature measurements, loss of flow transients, load transients, reduced primary system pressure operations and reduced element flow. The thermal and hydraulic conditions prevailing in these tests, including steady state and transient burnout rations, are developed. The effects of reduced system pres… more
Date: February 28, 1962
Creator: Bradley, P. L. & Coombe, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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