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Startup and Initial Testing of SM-1 Core II With Special Components

Description: The loading operation for SM-1 Core II is described. Results of startup physics measurements (Test A-300 (Series) and fission product iodine monitoring in the primary coolant are given. The SM-1 Core II initial loading progressed satisfactorily, fulfilling the predictions of the zero power experiment performed at the Alco Criticality Facility. The initial cold clean five rod bank position was 6.53 in.; the initial hot, no xenon, five rod bank position was 9.62 in.; the initial hot, equilibrium … more
Date: February 28, 1962
Creator: Moote, F. G. & Schrader, E. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Controls Reliability and Maintenance at the ORR

Description: Early evaluation and study of the various criteria for the ORR clearly established the requirements for the fundarnental safety and control instrumentation, and the instrumentation was well integrated into the design and construction of the plant. However, it was not designed for the optimum of maintenance convenience and minimum reactor down time in the event of instrument failure. The revisions and additions that have been made in the physical plant and maintenance which have resulted in a de… more
Date: August 28, 1962
Creator: West, K.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparison of Gaseous Waste Handling Systems for PL-3

Description: Gaseous waste handling systems are compared for direct and indirect boiling water and pressurized water reactors for PL-3 application. Areas that are common to the various concepts are not discussed since they do not enter into a comparison study. The major differences present are in the handling of active gases released to or held in the primary system coolant. These gases which could be present, their possibIe release from the system, and the necessary processing requirements are discussed in… more
Date: February 28, 1962
Creator: Noble, J. H. & Duke, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Primary Shield Optimization Survey for the PL-3 Reactor

Description: A detailed study of four reactor and shield configurations was made. Two basic reactor types, the boiling water and pressurized water reactors were considered. Shield materials of lead-water and iron-water were used with varying thicknesses for determining the optimum shield configuration for the PL-3 reactor. Also presented is a survey of available shielding codes. (auth)
Date: June 28, 1962
Creator: Scoles, J. F. & Crouch, A. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Technology Quarterly Progress Report, October-December 1961

Description: The ICPP processed Al fuel, prtncipally of the MTR-ETR type, durtng this quarter. Newly designed and installed processing equipment exhibited excellent operating performance. This included direct-air-pulsed extraction, stripping and scrub columns, and a cascade-controlled continuous evaporator in first cycle product concentration service. Aqueous zirconium fuel processing studies continued with the objective of adapting the hydrofluoric acid process to continuous dissolution-complexing to incre… more
Date: March 28, 1962
Creator: Bower, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE OAK RIDGE RESEARCH REACTOR (ORR), THE LOW-INTENSITY TESTING REACTOR (LITR), AND THE OAK RIDGE GRAPHITE REACTOR (OGR) AS EXPERIMENT FACILITIES

Description: >Characteristics of the ORR, LITR, and OGR that experimenters have found to be important are listed. The results of a survey conducted among experimenters on the utility of the reactors for various types of experiments are discussed, and some changes which might be made to improve the utilization are listed. A brief outline, with references, of most of the experiments currently being performed is included. (auth)
Date: August 28, 1962
Creator: George, K.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF FREEZE VALVE FOR USE IN THE MSRE

Description: Three types of frozen-seal valves'' were tested for possible use in the MSRE. The seal was melted by direct resistance heat, by induction heat, and by clamp-on Calrod heat. The frozen seal was made in a preformed restriction section of a standard piece of pipe by a cooling-gas jet stream directed at the restriction. All three valves performed satisfactorily through 100 test cycles. The Calrodheated valve was selected for MSRE use on the basis of simplicity of design and of operation. Two of the… more
Date: February 28, 1962
Creator: Richardson, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Improved Zirconium Alloys Annual Report: 1961 - 1961

Description: Annual technical report describing the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between February 1, 1961 to February 28, 1962 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: February 28, 1962
Creator: Weinstein, Daniel & Holtz, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Low Temperature Polymorphic Transformations of Calcined Alumina

Description: The factors which affect the transformation of amorphous alumina to crystalline alumina in the temperature range 350 to 650/sup 0/C were studied. Amorphous alumina, with small amounts of added impurities, was heated in an atmosphere containing the oxides of nitrogen, air, and water vapor, and the amount of crystalline alumina was determined. Alpha alumina was the predominant crystalline form after heating amorphous alumina that was prepared in a fluid bed calciner. The effects of temperature, c… more
Date: September 28, 1962
Creator: Murray, R. F. & Rhodes, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Wall and Bulk Temperatures for Fluids Flowing in Concentric Annuli

Description: From introduction: "This brief paper deals with the subject of radial temperature differences for heat transfer to fluids flowing through concentric annuli under the following conditions and assumptions: a. constant heat flux; b. fully-established turbulent flow; c. heat transfer through inner wall only; d. physical properties independent of temperature."
Date: May 28, 1962
Creator: Dwyer, Orrington Embry, 1912-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Review of Hanford Power Level Limits

Description: As for any nuclear reactor, the operation of the Hanford reactors is governed by many technical and administrative considerations. With the completion of current project action, later this year, certain of the technical limitations on reactor power level will be relieved, notably at the K Reactors, At that time, the technical and engineering limitations will be more liberal at some reactors than required for operation at the administrative power level limits, imposed by the Atomic Energy Commis… more
Date: June 28, 1962
Creator: Van Wormer, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Relocation of radial enrichment at the K reactors to decrease enrichment inventory

Description: The enrichment inventory required in the Hanford reactors is greatly dependent on the location of the radial enrichment ring. Present and past philosophy has dictated that the radial enrichment be located as close to the periphery of the reactors as possible, consistent with total control criteria, to obtain maximum flattening efficiency. As long as individual tube power limits dictate total pile power this philosophy of maximum flattening is consistent with a goal of maximum production. For th… more
Date: March 28, 1962
Creator: Kosmata, A. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculated fission product release from PRTR rupture

Description: Approximately 15 minutes after shutdown on August 21, 1962, evidence of a rupture was observed in the form of high radiation levels in the containment vessel and rupture monitor indications. Discharge of a special MgO-PuO{sub 2} test element revealed a cladding break of about 1.5 inches in length and about 1/4 inch wide in the widest place, located 36 inches from the top of the fuel element as it would have been oriented in the reactor. A visual examination in Radiometallurgy revealed that appr… more
Date: September 28, 1962
Creator: Stoddard, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary hazards review: Overboring Hanford reactors (condensed version)

Description: This is a condensed version of an extended hazards safety review of a proposal to modify the six 8 3/8-inch lattice reactors on the Hanford site. The review was intended to satisfy the specifications for a Preliminary Hazards Review as adopted at the third meeting of the General Electric Technological Hazards Council at New York City on June 15-16, 1961. This supplement is a tabular condensation of the information in the general document. One departure is made from the specifications for such a… more
Date: August 28, 1962
Creator: Nilson, R. & Carlson, P. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comprehensive Technical Report, General Electric Direct-Air-Cycle Aircraft Nuclear Propulsion Program, Program Summary and References

Description: This is one of twenty-one volumes sumarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This volume discusses the background to the General Electric program, and summarizes the various direct-air-cycle nuclear test assemblies and power plants that were developed. Because of the requirements of high performance, low weight, and small size, vast improvements in existing technology were required to meet the flight objectives. The technological progress achieved during… more
Date: June 28, 1962
Creator: Thornton, G. & Rothstein, A.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design of production test IP-468-A-FP, program for evaluation of alpha extruded fuel cores

Description: The alpha phase extrusion of dingot bars to rods for core blank heat treatment at MCW offers a three-fold incentive, including: (1) establishment of an independent alternate source of uranium cores, (2) a slight cost improvement of MCW extrusion over FMPC rolling of dingot and (3) potential improvement in core quality and performance. The purpose of this test is two-fold: (1) to evaluate gross dimensional stability and (2) to evaluate the gross irradiation performance of alpha phase extruded di… more
Date: January 28, 1962
Creator: Clinton, M. A. & Hodgson, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Instrumentation studies, Status report 2 (High level rate-of-rise)

Description: The purpose of this document is to present the latest results of a continuing instrumentation study being conducted by Research and Engineering. In a previous report results of 1-and 6-node calculations, for percentage- and fixed temperature-trip instrumentation were presented. These results were used to obtain a general understanding of the problem and to assess the value of using a multinodal approach. Calculations to determine the amount of protection provided by linear rate and period instr… more
Date: November 28, 1962
Creator: Stiede, W. L. & Monnie, D. I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test IP-508-D irradiation of a porous stainless steel clad fuel element assembly

Description: A large number of irradiation tests have been conducted with UO{sub 2} fuel elements to characterize the behavior of Zircaloy cladding when cooling water is allowed to penetrate the cladding to the fuel core. The test element, is designed so that cooling water will be in contact with the surface of the UO{sub 2} fuel core during irradiation. The irradiation behavior of the UO{sub 2} will be compared to the behavior of similarly irradiated, non-defected UO{sub 2} fuel-elements. Several character… more
Date: May 28, 1962
Creator: Marshall, R. K. & Cox, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Draft Rift Hazards Summary Review

Description: This document presents the Westinghouse Astronuclear Laboratory contribution to the RIFT flight safety review. While the presented herein is the best data that exists at this time, it can not be considered the final data. In consideration of the extremely dynamic nature of the program , it is intended to issue periodic revisions reporting new developments in the Westinghouse program.
Date: November 28, 1962
Creator: Kraig, H.I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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[News Script: Fridge]

Description: Script from the WBAP-TV/NBC station in Fort Worth, Texas, covering a news story about Benjamin Fridge, who addresses a convention of the Texas Wing of the Air Force Association, where he praises Fort Worth for its fine community relations with Air Force personnel.
Date: July 28, 1962
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Script
Partner: UNT Libraries Special Collections
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