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PHASE SHIFTS IN pi+ -p SCATTERING AT 310 Mev

Description: In an experimental program recently completed at the 184-inch synchrocyclotron in Berkeley, data were obtained on elastic {pi}{sup +}-p scattering at a laboratory energy of 310 Mev. Quantities measured were the differential cross section, the total cross section, and the polarization of the recoil protons as a function of center-of-mass angle. We have analyzed the data in terms of S, P, and D waves and have obtained only one acceptable solution. The resultant set of phase shifts is of the Fermi… more
Date: November 18, 1959
Creator: Foote, James H.; Chamberlain, Owen; Rogers, Ernest H.; Steiner,Herbert M.; Wiegand, Clyde & Ypsilantis, Tom
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Development and Evaluation of High-Temperature Tungsten Alloys : Summary Report

Description: Abstract: "Tungsten-rich alloys, developed for use at temperatures up to 2000F, exhibit ductility, fabricability and joinability not found in commercially-available materials. An envelope type of microstructure was produced in compositions containing at least 90 wt% tungsten by liquid-phase sintering of cold-pressed powders in hydrogen. At room temperature the alloys could be rolled extensively, and tensile elongations up to 25% were noted. Strength properties of a W-Ni-Fe base were improved by… more
Date: November 12, 1959
Creator: Holtz, F. C. & Van Thyne, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Waste disposal criteria existing reactor expansion study

Description: This document discusses waste disposal criteria were established on the basis that the occurrence of river flow rates which were 72 cents of normal would not cause the effects of waste disposal to exceed limits. Since even the base case exceeds the criterion for the average body burden of phosphorus-32, provision to reduce the output of this radioisotope must be included in any expansion program. Provision to reduce the output of other radioisotopes will be required for most cases where the bul… more
Date: November 17, 1959
Creator: Hall, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PT-IP-269-A-FP, evaluation of the stability of cores from extruded tubes

Description: If material received under this program is deemed acceptable for reactor charging, this test will authorize irradiation of fourteen monitor columns which shall be discharged at 200, 400 and 800 MWD/T to observe the performance of this material. This test shall run concurrently with irradiation of quantities up to 60 tons/month to be authorized separately.
Date: November 2, 1959
Creator: Hall, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Single tube flow rates at low header pressures with nozzle caps removed: All reactors

Description: Laboratory data of flow rate versus header pressure were obtained for various conditions of nozzle cap removal from C, K and BDF single tube mockups of central zone tube assemblies using I&E slug charges. The data are presented. Suggestions are made for applying the data to DR and H reactors. In general, the effect of a pre-inserted support charge on the flow rate is small, especially with the front nozzle cap on. It should be noted that pre-insertion of an entire (117 inch long) support charge… more
Date: November 20, 1959
Creator: Waters, E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Palm content of production metal

Description: Purpose of this study was to determine the {sup 237}Np input to the Purex process. The {sup 237}Np content of 639 g Pu/ton U irradiated fuel was found to be 1.78 {plus_minus} .09 g/ton of uranium at the 95% confidence level. Standard recovery for the chemical method was 96.7%, 98.0% for the sampling.
Date: November 23, 1959
Creator: Campbell, M. H. & Swift, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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K Area hydraulic working curves and numerical results of PT IP-130A K Reactor trip-out test down to cross-tie backup

Description: During the course of process engineering work at the K Reactors, a wide variety of problems have been encountered where hydraulic information was required. This information was, obtained from various documents, from calcuations, and from actual tests run specifically to obtain the information. In order to simplify work of this nature in the future and to present a convenient means of obtaining information, the data so collected are summarized and graphed in this document.
Date: November 18, 1959
Creator: Benson, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Expansion program 190 Building studies results

Description: It is the objective of this study to investigate preliminary expansion program requirements for process water, as supplied by 190 Building equipment; from the point of view of practical pumping, flywheel and pump suction head requirements. These requirements are to be determined at this time in such a form and accuracy as to be useful in refined estimating for budget study purposes. In order to obtain the objectives of this study at this time it has been decided to consider five different condi… more
Date: November 25, 1959
Creator: Quackenbush, C. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiochemistry for the rupture of a tube in tube fuel element in KER Loop 3

Description: On the 0000--0800 shift, September 30, 1959, the delayed neutron monitor on KER Loop 3 gave a high coolant activity signal. Events occurred rapidly that tended to substantiate the possibility of a fuel element failure in this loop. KE reactor was shut down immediately thereafter. This report is being written to summarize the sequence of events prior to and those following the KE reactor scram and to discuss the results and significance of data from analyses on coolant and coupon samples taken f… more
Date: November 5, 1959
Creator: Perrigo, L. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report for October 1959

Description: Pu output from separations plant was less than scheduled, but year-to- date production exceeded commitment by 4%. The Palm recovery run in Purex was the most successful to date. UO{sub 3} production and shipments met schedule. Purex had two pump failures. When Purex 1WW was centrifuged and treated to recover Ce, most of it remained in the centrifugate; only 14% was recovered. The prototype Pu ozonator in Redox performed well. Test runs on an acid precycle flowsheet and a proposed internal recyc… more
Date: November 20, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiometallurgical examination of direct cast core fuel elements, PT-IP-93, (RM-318)

Description: This report discusses two of the direct cast core I & E fuel elements irradiated in C Reactor under PT-IP-93 which were received at the Radiometallurgy Laboratory for examination during July 1959. One of the elements was badly warped and distorted while the other of the same series had remained relatively unchanged. Both pieces had received an average exposure of 689 MWD/T. Warp and diameter measurements show that the one element had warped approximately .040 in. and had become distorted in two… more
Date: November 12, 1959
Creator: Teats, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hot-Pressure Bonding of OMR Fuel Plates

Description: Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date: November 15, 1959
Creator: Alm, G. V.; Binstock, M. H. & Garrett, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Terminal Status Report for the Processing Refabrication Experiment

Description: Introduction: A low-capacity, low-decontamination plant can be built, as part of a power reactor complex, to avoid long distance transfer of fuel to a high-capacity aqueous processing plant. Activation of such a complex, with the processing plant adjacent to the reactor it serves, could decrease the cost of the integrated fuel cycle. The study of this concept is a major objective of the Processing Refabrication Experiment (PRE).
Date: November 15, 1959
Creator: Sinizer, D. I.; Mattern, K. L. & Kendall, E. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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