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NPR Physics Startup Testing Program

Description: The New Production Reactor, as compared to existing Hanford reactors, employs new and unique design concepts. To properly evaluate these design concepts and their effects on reactor operations, nuclear safety, and reactor life, a comprehensive testing program is planned; this program, with its objectives and restrictions, is discussed in this report. It has been developed along the same line as the C and K Reactors test, programs, and is expected to require a total time of 6--8 weeks of round-t… more
Date: April 25, 1962
Creator: Bowers, C. E.
Partner: UNT Libraries Government Documents Department
open access

Conceptual Design for a 75 MWE Mixed Spectrum Superheating Reactor Power Plant

Description: The design, performance, and cost information on the nuclear portion of the Mixed Spectrum Superheater power plant are emphasized. The research and development programs required to ensure plant feasibility are also presented. The nuclear steam supply system, reactor auxiliary systems, radiation control systems, control and instrumentation, special test instrumentation, plant operation and maintenance, steam cycle, turbine plant, general service systems, preliminary safeguards considerations, ex… more
Date: February 25, 1962
Creator: Brynsvold, G. V.; Hikido, K.; Reynolds, A. B. & Riley, D. R.
Partner: UNT Libraries Government Documents Department
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Final report: Irradiation performance of a coextruded, Zircaloy-2-clad three-rod cluster fuel elements, PT-IP-186-A

Description: One of the early candidate fuel elements for N Reactor use was the coextruded, Zircaloy-2-clad seven-rod cluster. As part of the program of evaluating the seven-rod cluster geometry, three-rod cluster fuel elements, two and three feet long, were irradiated. These long cluster fuel elements were irradiated to determine the distortion (or sag) which might occur at the center of the unsupported length during irradiation. Two three-rod clusters made up of 0.630 inch diameter rods, containing natura… more
Date: July 25, 1962
Creator: Call, R. L.
Partner: UNT Libraries Government Documents Department
open access

Low exposure irradiation of an enriched seven-rod cluster in KER Loop 1, PR-IP-246-A: Final report

Description: One of the early candidate fuel elements for the N Reactor was the seven-rod cluster fuel element. An objective of the program to determine the suitability of the seven-rod cluster fuel element for N Reactor use was to evaluate the irradiation performance of coextruded, Zircaloy-2-clad, seven-rod cluster fuel elements over a range of exposures from low exposures to high exposures. This report describes the irradiation testing of an enriched seven-rod cluster fuel element which was irradiated to… more
Date: July 25, 1962
Creator: Call, R. L.
Partner: UNT Libraries Government Documents Department
open access

Measured vs calculated river {Delta}T

Description: River temperature traverse data within and just the plant boundary are quite limited. For this report, traverse temperatures were calculated by first averaging the depth measurements vertically at each traverse point, and then weighing the average for the cross section by the depth at each point and the span between points. Calculated {Delta} T`s were determined by dividing the total reactor power level above the traverse line by the river flow, with the appropriate factor to obtain the correct… more
Date: October 25, 1962
Creator: Corley, J. P.
Partner: UNT Libraries Government Documents Department
open access

Summary of HRT Run 25

Description: Run 25 was the final period of power operational of the HRT. The reactor was operated for periods of 62, 8, 52, and 80 hours at 5 Mw with no outward indication of fuel and core and blanket average temperatures of 270 and 230 deg C, respectively. The uranium concentration in the was 1.7 to 2.0 g U/kg D/sub 2/O. Longer periods of operation were prevented by mechanical difficulties, notably with the fuel feed pump. While the reactor was subcritical after the last of the above runs, the upper patch… more
Date: July 25, 1962
Creator: Engel, J. R.; Bauman, H. F.; Buchanan, J. R.; Haubenreich, P. N.; Piper, H. B. & Richardson, D. M.
Partner: UNT Libraries Government Documents Department
open access

GRAPHITE-STAINLESS STEEL COMPATIBILITY STUDIES

Description: S>The compatibility of type 304L stainless steel in intimate contact with graphite is being studied as a function of temperature and contact pressure. This study is an outgrowth of materials compatibility problems in present and advanced gas-cooled reactors, where structural members in direct contact with graphite provide the possibility of both carburization and self-welding. Initial studies were concerned with surface reactions in the absence of gaseous contaminants under a vacuum of 10/sup -… more
Date: September 25, 1962
Creator: Fleischer, B.; DeVan, J. H. & Coobs, J. H.
Partner: UNT Libraries Government Documents Department
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Technical specifications, Hanford production reactors

Description: These technical specifications are applicable to the eight operating production reactor facilities, B, C, D, DR, F, H, KE, and KW. Covered are operating and performance restrictions and administrative procedures. Areas covered by the operating and performance restrictions are reactivity, reactor control and safety elements, power level, temperature and heat flux, reactor fuel loadings, reactor coolant systems, reactor confinement, test facilities, code compliance, and reactor scram set points. … more
Date: June 25, 1962
Creator: Gilbert, W. D.
Partner: UNT Libraries Government Documents Department
open access

THE DEFLECTING MODE IN THE CIRCULAR IRIS-LOADED WAVEGUIDE OF A RF PARTICLE SEPARATOR. Internal Report

Description: An analysis is presented of the deflecting mode in an iris-loaded synchrotron waveguide which is not based on the concept of TE and TM modes as generating fields. The solutions employed are derived from the transverse components of the electric and magnetic Hentzian factors. Their use avoids the singnlarities in the field expressions for phase velocities equal to that of light, which must occur with TE and TM modes. The fundamental properties of the hybrid solutions are exposed. The lowest mode… more
Date: October 25, 1962
Creator: Hahn, H.
Partner: UNT Libraries Government Documents Department
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Hallam Nuclear Power Facility, Preoperational Test Interim Report Dry Excess Loading

Description: A test to obtain data for use in determining the reactivlty wohh of Na in the Hallam reactor core is described. The test is designed to obtain information on the dry temperature coefficient of reactivity and to train operators. An evaluation of results is included. (J.R.D.)
Date: February 25, 1962
Creator: Kempt, H. C. & Corcoran, W. P.
Partner: UNT Libraries Government Documents Department
open access

Murgatroyd-an Ibm 7090 Program for the Analysis of the Kinetics of the Msre

Description: An addition is presented for the IBM-7090 program MURGATROYD to produce a rough graph of reactor power versus time. A sample of output is included for the case given as an example. (J.R.D.)
Date: May 25, 1962
Creator: Nestor, C. W. Jr.
Partner: UNT Libraries Government Documents Department
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Preliminary hazards review overboring Hanford reactors

Description: The General Electric Company, as prime contractor to the AEC at Hanford, is proposing to modify the lattice characteristics of the 8 3/8-inch lattice reactors for the purposes of improving the conversion ratio of these reactors. The proposed overbore modification of the reactors would remove the existing aluminum process tubes, enlarge the diameters of the graphite channels by about one-half inch, insert smooth-bore Zircaloy-2 process tubes and refuel the reactor with larger size, self-supporte… more
Date: July 25, 1962
Creator: Nilson, R. & Carlson, P. A.
Partner: UNT Libraries Government Documents Department
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Horizontal control rod corrosion, KW Reactor

Description: On September 19, 1961, the No. 3 horizontal control rod at KW reactor was removed after an apparent failure of the wall separating the boron carbide powder from the coolant water. The instrument indications that were interpreted as a rod failure include: high radiation alarms in the exhaust air, unexplained gain in reactivity, increasing coolant outlet temperature on No. 3 HCR, and high radiation readings of the outlet water from No. 3 HCR. The possible reactor safety aspects of such a failure … more
Date: May 25, 1962
Creator: Renberger, D. L.
Partner: UNT Libraries Government Documents Department
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Shield dome end plenum spacing

Description: No Description Available.
Date: September 25, 1962
Creator: Rieke, K.L.
Partner: UNT Libraries Government Documents Department
open access

A Program of Basic Research on Mechanical Properties of Reactor Materials. Quarterly Progress Report for the Period Ending June 30, 1962

Description: The effect of modifying the dislocation structure by room-temperature prestraining on the subsequent yielding behavior at 77 deg K is being studied. Results on tantalum single crystals indicated that a considerable decrease in the early yield stress for a given strain is effected by prestraining at room temperature. Twinning was observed in the tantalum at 77 deg K and normal rates of strain. It is shown that the potential barrler to dislocation motion in crystalline solids can be measured in r… more
Date: July 25, 1962
Creator: Trozera, T. A.; Flynn, P. W.; Chambers, R. H. & White, J. L.
Partner: UNT Libraries Government Documents Department
open access

Development of a Fluidized Bed Calcination Process for Aluminum Nitrate Wastes in a Two-Foot-Square Plant Calciner. Part 2. Factors Affecting the Intra-Particle Porosity of Alumina

Description: A seven- to twenty-fold volume reduction can be obtained from fluidized bed calcination of aqueous aluminum nitrate wastes, depending on the operating conditions employed and their effect on the intra-panticle porosity and absolute density of the calcined alumina. Among the calcining variables, only the bed temperature and the fuel aluminum concentration had a significant effect on the intra-particle porosity of alumina generated during studies conducted primarily in a two-foot-square fluidized… more
Date: July 25, 1962
Creator: Wheeler, B. R.; Grimmett, E. S. & Buckham, J. A.
Partner: UNT Libraries Government Documents Department
open access

Experimental Beryllium Oxide Reactor Program. Quarterly Progress Report for the Period, January 1 Through March 31, 1962

Description: Progress made in the development of the Experimental Beryllium Oxide Reactor (EBOR) is reported. The objective of the EBOR program is to develop a gas-cooled, beryllium oxide-moderated reactor which can be used in conjunction with a closed-cycle gas turbine or a steam cycle for a small land-based or a maritime power plant. Progress is reported on reactor development, reactor physics, and materials development. (N.W.R.)
Date: April 25, 1962
Partner: UNT Libraries Government Documents Department
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