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[Letter from Jerome K. Crossman to Carl P. Collins, February 22, 1965]

Description: Letter from Jerome K. Crossman to Carl P. Collins regarding an exchange of money. Crossman has sent Collins a $20,000 check from the Dallas Citizens' Interracial Association to fund the construction of the browsing area in a library Collins plans to build. The money is a gift from the association and Crossman wants Collins to recognize the association and the Board of Directors on the plaque. The Board of Directors includes the elected officials and prominent members of the Dallas Citizens' Interracial Association.
Date: February 22, 1965
Creator: Crossman, Jerome K.
Partner: UNT Libraries Special Collections

Geologic map and sections of the Thirsty Canyon SE quadrangle, Nye County, Nevada

Description: Preliminary 16 x 7.5 minute map of the Thirsty Canyon quadrangle, showing geology, roads, drainage, meridians and parallels, triangulation stations, and air-photo centers and wing points.
Date: February 1965
Creator: Lipman, Peter W.; Quinlivan, W. D.; Carr, Wilfred James & Anderson, R. Ernest
Location: None
Partner: UNT Libraries Government Documents Department
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Photoelastic evaluation of Phoebus 2 main closure design

Description: A two dimensional photoelastic study of two designs of clamps for the Phoebus 2 main closure is detailed. Predicted prototype stress data is given in the form of a stress parameter which includes the axial load and a representative clamp radius.
Date: February 5, 1965
Creator: Fischer, M. A.
Partner: UNT Libraries Government Documents Department
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Design and Operating Experience of the ESADA Vallecitos Experimental Superheat Reactor (EVESR)

Description: Summary: "The various design features significant to superheat are described for the 12-1/2 MW., 960 psig, 1050° F, steam-cooled, low-enriched, annular-fueled, experimental superheat reactor built by the General Electric Company at the Vallecitos Atomic Power Laboratory. Results obtained during the first six months of full-power operation, on the emergency cooling system, core thermal performance, and pressure vessel temperatures are presented and compared with predictions. Operating experience with over-all reactor system is also discussed."
Date: February 1965
Creator: Ianni, P. W.; Fritz, J. R. & Law, D. D.
Partner: UNT Libraries Government Documents Department
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Technical feasibility of using uranium oxide fuels at Hanford

Description: The use of uranium oxide fuel and the dispensing with metallic fuel elements in the Hanford production reactors have been contemplated in the past but have not been examined in any detail. This report reviews the technical feasibility of using oxide fuel and discusses the reactor limitations and changes in plutonium and isotope production. These results are based on preliminary calculations and a research and development program would be required to establish the validity of the calculated values. The research and development program is estimated to require $3.6 million over a three-year period. Technical aspects of using oxide are discussed in general for N, K, and the smaller reactors. The variations in uranium-to-graphite weight ratio and operating conditions vary the limitations encountered with each reactor type with an oxide fuel cycle. Plutonium separation and uranium oxide recycle on site have been examined, and a technical review of the limitations and the additional process requirements are presented.
Date: February 15, 1965
Partner: UNT Libraries Government Documents Department
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Pressure drop characteristics of solid aluminum dummy patterns in K Zircaloy-2 process tube

Description: Pressure drop tests were performed in the 189-D-Hydraulics Laboratory to determine the number of K-Reactor solid aluminum pieces (SAs) required to throttle the tube flow of a 46-piece KVE and a 38-piece KVN arch-rail I&E fuel charge to that of a corresponding bridge-rail charge. In addition, the effects on Panellit pressure and tube flow were determined for several cases.
Date: February 16, 1965
Creator: Angle, C. W.
Partner: UNT Libraries Government Documents Department
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Research and Engineering Operation Irradiation Processing Department monthly record report, January 1965

Description: Process and Reactor Development progress includes depleted uranium irradiation in the B and KE reactors and thoria irradiation in the B, C, D, KE, and KW reactors. Reactor Engineering reports on higher graphite temperature tests, graphite strength tests, heat removal requirements following reactor shutdown, and reactor deactivation. Reactor Physics topics include: E-Q loading, test facility loss of coolant protection, ball 3X replacement, and in-core flux monitors. Radiological Engineering reports on radiation control experience, classification, radiation occurrences, effluent activity data, radiation standards and controls and procedures, and dose rates in the DR reactor block. Also listed are many revised standards issued during the report period. Operational Physics Operations report on pile physics plant assistance for the B, C, D, DR, F, H, KE, AND KW reactors. Process Physics studies include reactivity and control studies and product related studies.
Date: February 3, 1965
Creator: Greager, O. H.
Partner: UNT Libraries Government Documents Department
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Examination of furnace belt failure in 232-Z incinerator

Description: Metallographic examination has been completed on samples from the Nichrome V wire mesh furnace belt in the 232-Z building incinerator. During service the furnace belt had broken in several places where the wire was welded together. A grain boundary phase was found in weld metal during metallographic examination of the as received material. It is probable to conclude that the failure during service was caused by accelerated corrosion of the weld and that the accelerated corrosion in that area was related to the structure of the weld metal. It would be informative to examine welds from the furnace belts that have not failed to further study the cause for the failure.
Date: February 11, 1965
Creator: Nelson, T. C.
Partner: UNT Libraries Government Documents Department
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Production Test IP-719: The effect of water plant variables on effluent activity. Final report

Description: One source of the parent materials which are converted into the radioisotopes in reactor effluent is the impurity content of Columbia River water. It has been demonstrated that as the efficiency of removal of the radioisotope parent materials increases, the amount of radioisotopes in the reactor effluent decreases. An example of this is the activity reduction which results from the use of high alum feed. In order to determine whether effluent activity would be influenced by the length of filter run, a half-plant test was initiated at DR Reactor on September 28, 1964, under the authorization of Production Test IP-719. This report presents the results of the test. The water treatment plant at DR Reactor was operated for a three-month period with half the filters on a seven-hour filter cycle and the other half on a 5.25 hour filter cycle. The shorter filter cycle did not significantly reduce either the filtered water turbidity or the P{sup 32} and As{sup 76} concentration in the reactor effluent. It can be concluded that in the range investigated effluent activity is not influenced by the length of filter cycle as long as breakthrough is avoided.
Date: February 23, 1965
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
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Radiochemical analyses of water samples collected postshot in the vicinity of Tatum Dome, Mississippi. Technical letter: Dribble 42

Description: On the basis of the analytical methods used, preliminary radiochemical analysis of the water samples collected after the Salmon event indicate that no detectable level of radioactive contamination exists. Samples were obtained from the calcite caprock at a depth of 934 to 1,006 feet and through intervening aquifers to aquifer 1 at a depth of 365 to 421 feet from the surface. The water sample collected from the calcite caprock was taken within approximately 1,700 feet of the detonation. Periodic sampling of the wells will continue and more refined analytical techniques will be used in analyzing the samples. After the hydrologic test wells have been better developed by bailing, additional isotopes will be investigated.
Date: February 8, 1965
Creator: Janzer, V. J. & Rucker, S. J.
Partner: UNT Libraries Government Documents Department
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Computer calculation of angular momentum coupling coefficients and of (d,p) stripping reaction cross section. Technical report No. 14. [B53 DWC, B53GOR, B53RIM, B53SIX, in FORTRAN]

Description: A theoretical expression for the stripping differential cross section is derived and prepared for computer evaluation. Input information is provided for the code B53DWC, which calculates this cross section, and the codes B53GOR, B53SIX, and B53RIM, which evaluate 3-J, 6-J, and 9-J coefficients. (RWR)
Date: February 1, 1965
Creator: Strobel, G.L.
Partner: UNT Libraries Government Documents Department
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