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EURATOM PROGRAM "Improved Zirconium Alloys"

Description: Introduction: "This report is an expanded version of the regular monthly letter report and is prepared in this form with the intention of reviewing work on the subject program for Euratom technical personnel. Work performed during the month of September, which normally constitutes the entire letter report, has been condensed under one heading."
Date: October 5, 1960
Creator: Weinstein, Daniel & Van Thyne, R. J.
Partner: UNT Libraries Government Documents Department
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The Boron-Carbon System: Quarterly Report Number 1, May - June 1960

Description: Abstract: A definitive investigation of the boron-carbon equilibrium system is being made by X-ray diffraction, metallographic, and thermal analytical techniques. Alloys are being produced by sintering pressed powder aggregates with subsequent arc melting. Alloys have been made at two atomic percent intervals up to thirty atomic per cent carbon. In the future, higher carbon compositions are to be investigated. Techniques have been worked out for the metallographic preparation of the extremely h… more
Date: August 5, 1960
Creator: Elliott, Rodney P. & Van Thyne, R. J.
Partner: UNT Libraries Government Documents Department
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Testing of Zircaloy-2-Clad Uranium Seven-Rod Fuel Elements. Final Report

Description: In 1955 the Fuels Development Operation began irradiation testing of fuel elements in high temperature water. It was assumed that if a new reactor were built at Hanford, it would be cooled by high-temperature, pressurized water. Corrosion tests showed that aluminum-clad production fuel elements could not be used in high-temperature water. Therefore, while work to improve the resistance of aluminum to high-temperature water proceeded, the Fuel Design Operation began irradiation of stainless stee… more
Date: July 5, 1960
Creator: Geering, G. T.
Partner: UNT Libraries Government Documents Department
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Xenon and Samarium reactivity effects associated with coolant loss

Description: In Hanford reactors the reactivity gain upon loss of coolant water is an important factor in the speed of control requirements. The reactivity gain in the cold, clean reactor is determined from experiments, but additional effects must be taken into account if the gain in the operating reactors is to be obtained. One of these effects is the change in Xenon and Samarium poisoning with neutron temperature, which is discussed here. Earlier work on the relationship of operating limits to the reactiv… more
Date: April 5, 1960
Partner: UNT Libraries Government Documents Department
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Qualitative aspects of neutron moderation with respect to graphite damage

Description: Under simplifying assumptions, an expression is obtained relating the integrated kinetic energy transferred to moderator atoms to the thermal neutron exposure in adjacent fuel. Reactor-dependent factors are explicit in the expression which make it possible to compare graphite contraction data from different reactors or to estimate graphite damage in a new reactor based oil observed damage in existent reactors. Graphite temperature, which may be an important factor in graphite contraction, is no… more
Date: May 5, 1960
Creator: Nilson, R.
Partner: UNT Libraries Government Documents Department
open access

Use of poison splines to reduce non-equilibrium losses, KE Reactor

Description: A significant reduction in non-equilibrium losses is possible through the use of poison splines for reactivity and heat distribution control during reactor startups. The curves presented show the results of an analysis of recent KE Reactor poison spline startup usage. These curves demonstrate the magnitude of gains possible at other reactors through the use of poison splines for turnaround control.
Date: February 5, 1960
Creator: Franklin, F. C.
Partner: UNT Libraries Government Documents Department
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Three-group NPR core flux levels

Description: In order to predict graphite damage rates for the NPE, it is necessary to have some knowledge of the neutron fluxes at various energy levels. In particular it is important to know flux levels relative to those existing where graphite samples have been irradiated experimentally. Three-group flux levels have been calculated for regions far from boundaries in the core of the NPR and of a K-reactor. The results reported here have been obtained from more detailed calculations using better cross sect… more
Date: January 5, 1960
Creator: Simpson, D. E.
Partner: UNT Libraries Government Documents Department
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Pressure required to overcome boiling at low tube powers: BDF reactors

Description: The purpose of this report is to present laboratory data concerning thermal and hydraulic changes which occur in a low power process channel during a flow interruption. The experiments were conducted in the Heat Transfer Laboratory of Thermal Hydraulics Operation.
Date: August 5, 1960
Creator: Waters, E. D. & Fitzsimmons, D. E.
Partner: UNT Libraries Government Documents Department
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PM-1 Nuclear Power Plant Program: 4th Quarterly Progress Report, December 1, 1959-February 29, 1960

Description: From abstract: The principal efforts during the fourth project quarter were the near-completion of the final design and preparation of specifications for plant components. Reactor development work included final preparations for the flexible zero-power test (PMZ-1) program and revised fuel element irradiation test program, continuation of reactor flow test, further work on heat transfer test program, and final design and fabrication of the prototype magnetic jack-type control rod actuators.
Date: April 5, 1960
Creator: Martin Company. Nuclear Division.
Partner: UNT Libraries Government Documents Department
open access

PM-1 Nuclear Power Plant Program: 5th Quarterly Progress Report, March 1, 1960-May 31, 1960

Description: From abstract: Reactor development work includes: initiation of the flexible zero-power test (PMZ-1) experimental program, fabrication and delivery of a PM-1 type fuel element, continuation of reactor flow and heat transfer tests, development work on rare earth control rods, and testing and redesign of the prototype magnetic jack-type control rod actuator.
Date: July 5, 1960
Creator: Martin Company. Nuclear Division.
Partner: UNT Libraries Government Documents Department
open access

KAPL-120-8A Test Assembly Thermocouple Failure.

Description: This document reports the circumstances surrounding the failure of sheathed thermocouples during a test being conducted in the KAPL-120 Loop. The report is prepared to provide a record of these events and to acquaint those who use these thermocouples for testing of other applications with the difficulties that are sometimes encountered.
Date: February 5, 1960
Creator: Dearing, F. E.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Fretting Corrosion of ZR-2

Description: Although the corrosion of resistance of Zircaloy--2 clad fuel elements in high temperature water is excellent, some concern has been expressed in regard to the resistance against fretting corrosion. Since this form of corrosion can proceed quite rapidly it could induce fuel element failure through penetration of the cladding. Fretting corrosion if it occurred, would take place either where the fuel element contacted the process tube or where portions of the fuel element contacted each other, e.… more
Date: February 5, 1960
Creator: Lobsinger, R. J.
Partner: UNT Libraries Government Documents Department
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Summary of Gummed Film Results Through December, 1959

Description: From Abstract: "The data for gummed film fallout measurements through December 1959 are reported. The bulk of the report consists of summary tables for each gummed film station listing the monthly estimates of strontium 90 deposition and infinity gamma dose."
Date: September 5, 1960
Creator: Harley, John H.; Hallden, Naomi A. & Ong, Long D. Y.
Partner: UNT Libraries Government Documents Department
open access

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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Evaluation of Aluminum for use in Reactors Cooled by High-Temperature Recirculating Water

Description: aluminum has been considered as a material for cladding fuel elements to be used in reactors cooled by high-temperature recirculating water. Aluminum is abundant, chap, has a relatively low cross section for thermal neutrons, and is readily fabricated into complex shapes. For these reasons, it appears that the use of aluminum rather than steel, Zircaloy or other candidate materials for fuel element cladding, would result in considerable savings in operating expense. The actual economics will of… more
Date: April 5, 1960
Creator: Ayres, J. A.
Partner: UNT Libraries Government Documents Department
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A Study of the Wear and Galling of Autoclaved Zircaloy-2 By Various Materials

Description: This is the third of a series of reports describing the phases of a study of the wear and galling of autoclavedZircaloy-2 by various bearing surface materials. The first report (1) showed that increasing contact area between the autoclaved Zircaloy-2 surfaces will not prevent scratching. It also showed that metals softer than Zircaloy-2 in general do not scratch it. The second report (2) described how eight metals and alloys were wear-tested on autoclaved Zircaloy-2 as prospects for fuel elemen… more
Date: July 5, 1960
Creator: Weber, J. W.
Partner: UNT Libraries Government Documents Department
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Strontium Sorption Studies Using Naturally Occurring Ion Exchange Materials

Description: Four naturally occurring materials, namely, vermiculite, variscite, Tennessee rock phosphate, and Florida pebble phosphate, were studied to determine the feasibility of their use in columns for the sorption of strontium from high pH, intermediate-level wastes produced at ORNL. Excepting vermiculite, all materials were found to be effective in strontium removal.
Date: December 5, 1960
Creator: Thomas, K. T.; Jacobs, D. G.; Tamura, T. & Struxness, E. G.
Partner: UNT Libraries Government Documents Department
open access

A Transport Calculation of the HFIR Beam Hole Currents

Description: An estimate was made of the beam hole currents to be expected from both the radial and tangential beam holes in the present HFIR design. The angular fluxes required for these calculation were determined by an 18-group, S8 transport calculation (SNG reactor code). Both type beam holes produced thermal neutron currents of 7.5 x 10^10 neutrons/cm^2 sec. at a power level of 100 Mw. The nonthermal component of the beam current was 7.0 x 10^10 and 4.5 x 10^10 neutrons/cm^2 -sec for the radial and tan… more
Date: December 5, 1960
Creator: Claiborne, H. C. & Rakavy, G.
Partner: UNT Libraries Government Documents Department
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