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in subjects: "21 Specific Nuclear Reactors And Associated Plants"  
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Army Gas-Cooled Reactor Systems program: alternator final design report

Description: The development and testing of a demonstration brushless alternator for the ML-1 mobile nuclear power plant is described. The brushless concept was selected after it became apparent that a conventional power generator could not satisfy the ML-1 weight and size requirements. The demonstration alternator fabricated and tested under this program did not meet all performance specifications; the efficiency was low and the unit could not be operated for significant periods of time without overheating… more
Date: June 1, 1964
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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New burnout correlation for annuli

Description: A number of burnout tests have been run subsequent to the publication of the burnout equations in DP-355 and DP-725. The range of variables was extended in these tests and the burnout heat flux was measured. This memorandum presents a modified empirical equation, which correlates the new data, for use in the design of fuel assemblies for the HWCTR. We expect to submit this material for a journal publication within the next quarter.
Date: March 26, 1964
Creator: Towell, R.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High-temperature materials program. Progress report No. 34, Part B

Description: Information is presented concerning coated fuel particle development and evaluation; burnup capabilities of Y/sub 2/O/sub 3/-stabilized UO/sub 2/ and stabilized fuel - BeO matrix materials; high-temperature studies of substoichiometric urania and urania solid solutions; high-temperature carbides and borides research; and high-flux reactor materials gaseous fuels research.
Date: April 15, 1964
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermo-physics technical note No. 37: SNAP- 10A, Stainless Steel-316 vessel wall ablation. Final report

Description: The altitudes and times of ablation have been determined for the SNAP-10A, SS-316 vessel wall reentering under various conditions. The results are confined to one typical location on the reactor and to one typical reentry trajectory. The location is the side wall of the vessel and the trajectory is the one used in NAA-SR-8303.
Date: December 7, 1964
Creator: Montgomery, L.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Process Heat Reactor Program. Quarterly progress report, February 1-April 30, 1964

Description: Work was continued on the development of a process for the gasification of bituminous coal with heat from a nuclear reactor. Major objectives of the project are: (1) develop and test components for a gas-cooled reactor system that can heat gases to 2000/sup 0/ to 2500/sup 0/F; (2) investigate coal gasification methods compatible with this system; and (3) develop an exchanger that can utilize high-temperature heat to gasify coal or heat chemical process streams. During the past year, work was co… more
Date: January 1, 1964
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Report on Carbon-14 generation and release at some of the Hanford reactors

Description: The Hanford graphite-moderated reactors have an enclosed gas circulation system to maintain control of the composition of gas atmosphere in the graphite stack. This investigation was undertaken to answer several questions concerning the generation and release of Carbon-14 in the operation of these graphite moderated reactors. The principle question was: Will an increase in the nitrogen content of the reactor atmosphere increase the release of Carbon-14 sufficiently to create a health hazard. Ot… more
Date: December 14, 1964
Creator: Barton, G.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of horizontal control rods in total control compensation

Description: This document provides a method for calculating the compensating effects of horizontal control rods in highly shadowed cases encountered in total control administration. The two-dimensional diffusion theory computer code ``9 ANGIE`` was used to calculate the reactivity effects of the horizontal control rod geometry with respect to total control requirements at B, D, F, and DR Reactors. For total control requirements in the center section of B, D, F, and DR Reactors the horizontal control rods w… more
Date: September 4, 1964
Creator: Vaughn, A. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Loading and operating conditions for a charge of eight enriched single tube elements, PT IP-544-A, Supplement A

Description: Supplement A, Production Test IP-544-A authorized the irradiation of 1.6 per cent enriched single tube elements in KER-1 and -2 and specified certain limitations on the operating conditions for the elements. The test required that specific operating conditions and trip settings for particular loadings would be approved by the managers of Testing, Process, and Reactor Development and Process Technology Subsections prior to charging. The purpose of this document is to provide the process the tube… more
Date: January 14, 1964
Creator: Knight, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Estimates of river dilution factors from upstream reactors

Description: This documents contains a table has been prepared to assist in the evaluation of hazards to occupants of the Wahluke Slope associated with radioactive liquids discharged to the river in the event of reactor accidents. Concentration ratios have been estimated for both the maximum point in the river as well as along the shoreline opposite the reactors for several locations of potential interest and for reactors in B, K, and D Areas. The shoreline concentrations apply to water up to 25 yards from … more
Date: June 15, 1964
Creator: Corley, J.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of test data on ablation of SNAP 2/10A fuel, aluminum, and stainless steel in an arc-heated wind tunnel

Description: A series of arc-jet tests were performed for the purpose of investigating the behavior of SNAP 2/10A fuel in a simulated reentry environment. The data from the tests (motion pictures and transient temperature distributions) were analyzed and compared with computations which used an energy balance to describe the heating of the fuel to its melting temperature. The dissociation of hydrogen was assumed to occur as an isothermal, endothermic phase change. This concept neglects the kinetics of diffu… more
Date: November 3, 1964
Creator: Arnold, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of pH and oxygen on stress corrosion cracking of stainless steel in reactor moderator service

Description: Intergranular cracking of Type 304 stainless steel outlet nozzles in reactor moderator service prompted a broad program of laboratory studies to determine the cause of the failures. It was demonstrated that sensitized and pickled Type 304 stainless steel is extremely susceptible to both intergranular and transgranular chloride stress corrosion cracking in hot water of pH 4.5 to 5.0 which contains as little as 2 ppM chloride ion. Although the chloride content of moderator is only about 0.01--0.0… more
Date: February 1, 1964
Creator: Rideout, S.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Answers to questions of the Advisory Committee on Reactor Safeguards relative to the need for retention of government land

Description: This report discusses a meeting scheduled with a Subcommittee of the Advisory Committee on Reactor Safeguards to review the future need for retention of government land on the Wahluke Slope. A number of questions were asked by the Washington AEC Division of Production as a basis for the discussions. This interim report provides answers to several of the questions.
Date: June 8, 1964
Creator: Junkins, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transient thermal-hydraulic experiments: N-Reactor inlet connector break

Description: An N-Reactor inlet connector piping break was investigated in a laboratory study to determine the effect of this break on the affected process tube`s thermal-hydraulic performance. A full-scale mock-up of the piping between the inlet and outlet risers was used which included actual reactor valves and fittings. An electrically heated half-length section which was equivalent to the downstream half of the reactor fuel column was used to model the heat-generating portion. The simulation of the conn… more
Date: September 14, 1964
Creator: Rowe, D. S.; Anderson, J. K. & Thorne, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal and nuclear design review of the NRX-A5 Reactor

Description: A thermal and nuclear NRX-A5 Design Review was held at WANL on April 10, 1964. Analyses and planning performed to date on the NRX-A5 and subsequent reactors were presented. Systems analyses were performed on various "cooled periphery".and "hot periphery" seal configurations. A number of inner reflector designs were examined, as well as means for cooling the lateral support springs. Core component redesign incl,uded methods for controlling inter-element pressure distribution by undercutting or c… more
Date: May 15, 1964
Creator: Black, D L; Minners, W; Stefanko, J S & Vijuk, R M
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design criteria fire and sanitary water modifications

Description: Water for fire and sanitary use in the older reactor areas is provided by pumps located in the 183 building of each particular area. Each area has two electrically driven pumps for normal use and two steam driven pumps in case of power failure. Distribution within an area is through an underground main loop with laterals to buildings and fire hydrants. When the DR, F and H Reactors are deactivated, fire and sanitary water in each area is still necessary for protection of the area and for certai… more
Date: September 3, 1964
Creator: Steele, C. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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