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B-Plant fission product flowsheets: Part 2

Description: The technical bases for Phase I of the Fission Product Program have previously been presented for Phase I design. This report represents its sequel for Phase II of the program. Phase I provides the means of segregating, concentrating, and aging crude fission product fractions with market value. Phase II is to provide the means for single-line purification and packaging of megacurie quantities of fission products (principally strontium-90). The technical bases for Phase II project scoping studie… more
Date: September 29, 1961
Creator: Rey, G.
Partner: UNT Libraries Government Documents Department
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Design Criteria for Irradiated Vessels Task 6.0 Summary Report

Description: Abstract: This technical report presents design criteria to prevent the brittle fracture of ferritic reactor vessels that cold occur as a result of the rise in NDT caused by fast neutron irradiation. The criteria require that maximum principal stress in the vessel does not exceed 18 percent of yield stress at temperatures below NDT + 60 degree F. Under certain conditions the allowable stress may be based on the irradiated yield stress. A discussion of brittle fracture and an explanation of the … more
Date: September 29, 1961
Creator: McLaughlin, D. W.
Partner: UNT Libraries Government Documents Department
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Numerical results of production test IP-326-I, low flow calibration tests at DR and C reactors, and of production test IP-395-I, removal of high tank discharge line strainer gates at B, D, and F reactors

Description: Low flow calibration tests have now been completed at all old reactors as a part of the program to determine the adequacy of the old reactor last ditch water backup system more accurately. In addition, the high tank discharge line strainer gates have been removed at B, D, and F reactors in order to increase the emergency high tank flow rates to the reactors and thereby increase high tank water backup adequacy. The purpose of this document is to list the results of the last two low flow calibrat… more
Date: September 29, 1961
Creator: Benson, J. L.
Partner: UNT Libraries Government Documents Department
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Reactivity and graphite temperature effects of a helium-nitrogen atmosphere. Final report of PT IP-358-AC

Description: The purpose of the production test was to {open_quotes}investigate the reactivity and temperature effects and the associated operating problems resulting from the use of nitrogen instead of carbon dioxide as a constituent of the K Reactor atmosphere.{close_quotes} This report summarizes the reactivity and reactivity-associated graphite temperature effects observed during the first four months of the test which was initiated at KE Reactor on December 5, 1960.
Date: September 29, 1961
Creator: Bailey, G. F.
Partner: UNT Libraries Government Documents Department
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Small Power Reactor Projects of the United States Atomic Energy Commission

Description: Information on small power reactor projects of the USAEC is summarized. General information concerning the projects as a whole is given. Specific projects discussed include: the Elk River Power Reactor, the Piqua Nuclear Power Facility, the BONUS Power Reactor, the Pathfinder Power Reactor, the small-size pressurized water power reactor, and the experimental low-power process heat reactor. (M.C.G.)
Date: September 28, 1961
Partner: UNT Libraries Government Documents Department
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Design Properties for Graphite

Description: This report addresses the design properties for graphite.
Date: September 27, 1961
Creator: Hoppe, A.W.
Partner: UNT Libraries Government Documents Department
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NPR Reactor shield calculations

Description: At the request of IPD Personnel, calculations on neutron and gamma attenuation were made for the NPR shield. The calculations were made using a new shielding computer code developed for the IBM 7090. The calculations show the thermal neutron flux, total neutron dose rate, and gamma dose rate distribution through the entire shield assembly. The calculations show that the side and top primary shield design is adequate to reduce the radiation level below design tolerances. The radiation leakage th… more
Date: September 27, 1961
Creator: Peterson, E. G.
Partner: UNT Libraries Government Documents Department
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LOW LEVEL WASTE TREATMENT BY ION-EXCHANGE, II. USE OF A WEAK ACID, CARBOXYLIC-&HENOLIC ION-EXCHANGE RESIN

Description: Laboratory results are presented for a flowsheet study of a process for decontaminating ORNL low level waste water. The water is adjusted to approximately pH 12 with NaOH, clarified, and passed through a bed of phenolic cation exchange resin. This study, using a phenoliccarboxylic resin, showed essentially the same results as those previously reported using a phenolic- sulfonic resin, i.e., radioactivities in ORNL waste were reduced to the order of 10% of MPC. The phenolic-carboxylic resin has … more
Date: September 25, 1961
Creator: Holcomb, R.R. & Roberts, J.T.
Partner: UNT Libraries Government Documents Department
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Low level waste treatment by ion-exchange. II. Use of a weak acid, carboxylic-phenolic ion-exchange resin

Description: Laboratory results are presented for a flowsheet study of a process for decontaminating ORNL low level waste water. The water is adjusted to approximately pH 12 with NaOH, clarified, and passed through a bed of phenolic cation exchange resin. This study, using a phenolic-carboxylic resin, showed essentially the same results as those previously reported using a phenolic-sulfonic resin, i.e., radioactivities in ORNL waste were reduced to the order of 10% of MPC. The phenolic-carboxylic resin has … more
Date: September 25, 1961
Creator: Holcomb, R.R. & Roberts, J.T.
Partner: UNT Libraries Government Documents Department
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PILOT PLANT SHUTDOWN AND Pu-Al PROCESSING

Description: The large aqueous pilot plant facilities at ORNL were cleaned and are being put in standby condition. Experience was gained during the year as anion exchange was used to recover more than one kg of plutonium left in the exploded evaporator system. This experience is being applied to a new recovery program just beginning in cell 1 of Building 4507. (auth)
Date: September 25, 1961
Creator: Bresee, J.C.
Partner: UNT Libraries Government Documents Department
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Summary Nuclear Calculations for the SM-2 Core 1

Description: The results of a limited analysis of the extended SM-2 critical experiments are given. A review of the analytical models is presented to ascertain the accuracy of the reactivity calculations for the reference SMi-2 Core I. A new reference B-l0 loading was derived based on analysis and experimental measurements. Calculations of power distributions and burnup behavior of the reference core are presented and comparisons to available measured data made. (auth)
Date: September 25, 1961
Creator: Fried, B. E.; Beam, R. H. & Bobe, P. E.
Partner: UNT Libraries Government Documents Department
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B and D downcomer prototype data

Description: Available pressure data on the B and D downcomers and approach piping is tabulated herein. All readings were taken with an air bubbler system; readings given in psi were taken on a Bourdon-type pressure-vacuum gauge, readings given in inches of water were read on an oil-filled manometer. In each case, fluctuations occurred and the mean value was estimated by eye. Data are presented as a function of flow rate and temperature.
Date: September 22, 1961
Creator: Corley, J. P.
Partner: UNT Libraries Government Documents Department
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Interim Report on the Development of an Air Pulser for Pulse Column Application

Description: The Idaho Chemical Processing Plant for several years has been studying various pulsing systems, used in extraction columns for processing irradiated nucIear fuel elements, in an effort to eliminate the mechanical difficuittes in present pulsing systems. An air puising system has been demonstrated, and a discussion is given of experimental work, pulser design, and plant operational experience with this system. It is concluded, from work completed thus far that air puising of extraction columns … more
Date: September 22, 1961
Creator: Weech, M. E.; P'Pool, R. S. & MacQueen, D. K.
Partner: UNT Libraries Government Documents Department
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Radioactivation Analysis

Description: The development of nuclear reactors and other sources of nuclear particles has provided the analyst with a new method which has been successfully applied to the determination of microgram and even submicrogram quantities of many elements. In this method, known as "radioactivation analysis," the element to be determined is "activated" through some type of nuclear reaction which produces a radioactive isotope of the element. Since the radioisotope produced decays with its own characteristic radia… more
Date: September 22, 1961
Creator: Leddicotte, G. W.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: August 1961

Description: This report, for August 1961 from the Chemical Processing Department at HAPO, discusses the following; Production operation; Purex operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; and special separation processing and auxiliaries operation.
Date: September 21, 1961
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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CHEMICAL TECHNOLOGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961

Description: Activities in research programs are summarized in the areas of power reactor fuel processing, fluoride volatility processing, molten salt reactor fuel processing, homogeneous reactor fuel processing, waste treatment and disposal pilot plant decontamination, GCR coolant purification studies, equipment decontamination, HRP thoria blanket development, fuel cycle development, transuranium element studies, production of U/sup 232/, uranium processing, fission product recovery, thorium recovery from … more
Date: September 21, 1961
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Annual Progress Report, May 31, 1961

Description: Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.
Date: September 21, 1961
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Partner: UNT Libraries Government Documents Department
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Performance characteristics modified low lift pumps 100-K Area

Description: A development program was initiated under Project CG-775 to test the proposed. process water pump modifications for Project CGI-883, Increased Process Water flow 100-K Area. Both the high lift and low lift pumps of the 190-KE pumping Unit were modified during May, 1959 for in-service prototype testing of the proposed equipment revisions. The testing proved the feasibility of the modification program but a problem, in the form of capitation damage to the high lift pump impeller, was noted. An in… more
Date: September 21, 1961
Creator: Keene, L. M.
Partner: UNT Libraries Government Documents Department
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Status of the High-Temperature Gas-Cooled Reactor

Description: The history of gas-cooled reactor developmert is reviewed. The 40-Mw HTGR r the Peach Bottom Power Plart is described. Other projects to follow this prototype are outlined. Fuel development and progress in graphite core technology are discussed. The program sponsored by the Empire State Atomic Development Associates for a high-temperature gas-cooled reactor with an output of 300 to 500 Mw(e) is described. (M.C.G.)
Date: September 21, 1961
Creator: LeClair, T. G.
Partner: UNT Libraries Government Documents Department
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Ecological Sampling and Meteorological Calculation of Fallout on Forests Near Oak Ridge

Description: Spatial patterns of radioactive contuamination on forest foliage were measured by gamma spectrometry and are discussed with respect to local vs. world- wide origin of the fallout and implications for ecology, health physics, and management of nuclear facilities. In September 1959, I/sup 131/ on dogwood leaf samples varied from over 500 mu mu c/g dry wt near Oak Ridge National Laboratory stacks to 1 to 7 mu mu c/g near the margins of the Oak Ridge Reservation. Stack fallout tended to occur close… more
Date: September 20, 1961
Creator: Olson, J.S.
Partner: UNT Libraries Government Documents Department
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Experimental boiling burnout conditions for Hanford production reactors

Description: The purpose of this report is to present some experimental data concerning boiling burnout and to discuss briefly the significance of these data in relation to the Hanford production reactors.
Date: September 20, 1961
Creator: Waters, E. D. & Batch, J. M.
Partner: UNT Libraries Government Documents Department
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