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Autologous Bone Marrow Transfusion Following Chemotherapy

Description: An aggressive attack in the management of malignant disease by chemotherapeutic means has been hampered by toxic effects of these agents on bone marrow, gastrointestinal tract, and skin.
Date: November 18, 1963
Creator: Meyer, L. M.; Fliedner, T. D. & Cronkite, E. P.
Partner: UNT Libraries Government Documents Department
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Operating limits -- Hanford Production Reactors

Description: This document provides Operating Limits which shall be applicable to the eight production reactor facilities, designated B, C, D, DR, F, H, KE and KW (hereinafter referred to as the Hanford Production Reactors) located at the Hanford site.
Date: November 5, 1963
Partner: UNT Libraries Government Documents Department
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Preliminary study of multiple fuel processing at the Purex Plant

Description: Processing of multiple types of irradiated fuel elements in Purex has been proposed to the Atomic Energy Commission as a means of realizing significant savings in overall CPD operating costs for weapons programs and permitting release of the Redox plant for non-weapons programs. The process and equipment requirements for implementing a multipurpose operations program have been under study in both plant and laboratory programs for processing slightly enriched Zircalloy-clad uranium metal fuels a… more
Date: November 26, 1963
Creator: Kendall, J. B.; Lambert, R. W. & Nielson, S. M.
Partner: UNT Libraries Government Documents Department
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A review of the philosophy and future use of the Ball-3X system in the IPD reactors

Description: Distortion of the graphite stacks of the Hanford IPD reactors due to neutron irradiation effects has grown to where major corrective or compensatory action must be taken to preserve the operability of the safety control systems and life of the reactors. For the past few years, the line has been satisfactorily held by an aggressive maintenance program and short-range solutions. However, longer range, more permanent solutions are needed and high priority is being given to studies toward these end… more
Date: November 6, 1963
Creator: Nilson, R.
Partner: UNT Libraries Government Documents Department
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Fabrication process test evaluation: Shipping, HI-74-SL

Description: The test parts were canned on October 7, 1962 and October 8, 1963. Only six parts, all radiographic rejects, were used for the test instead of 12 parts as originally planned. The original test called for using one very porous and one relatively non-porous sand cast aluminum insert in each container. Shipping experience has shown no significant effect of porosity of inserts on corrosion severity of parts shipped in them. All inserts used were full contour support inserts. Each test part was cann… more
Date: November 8, 1963
Creator: Barber, A. E.
Partner: UNT Libraries Government Documents Department
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A preliminary study of production of tungsten-rhenium alloys in N-Reactor

Description: Feasibility and cost data are supplied for the production of tungsten-rhenium alloys from tungsten targets in the N-Reactor. The two types of target elements assumed were: (a) tungsten containing 90 a/o tungsten-186, 9 a/o tungsten-184 and 1 a/o tungsten-183 and 182, and (b) tungsten of natural isotopic composition (28.4 a/o tungsten-186, 30.6 a/o tungsten-184, 14.4 a/o tungsten 183, and 26.4 tungsten-182). It is assumed that the average thermal neutron capture cross section for the tungsten-18… more
Date: November 19, 1963
Creator: Riches, J. W. & Pierick, E. G.
Partner: UNT Libraries Government Documents Department
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Comparative reactor flux spectra

Description: This document is explanatory in nature and is intended to clarify certain questions about reactor neutron flux spectra in various AEC production facilities. Simplified models are used to illustrate neutron ``temperature,`` spectral ``hardening,`` and the so-called ``Westcott R.``
Date: November 27, 1963
Creator: Gumprecht, R. O.
Partner: UNT Libraries Government Documents Department
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Analysis of E-N target conversion data

Description: Production efficiency studies of the E-N loading require that conversion ratio values for both plutonium and tritium be defined. Changing of the core-loading charge makeup with each core load to obtain a more efficient loading has theoretically resulted in increasing the tritium conversion ratio. Tritium recovery data from the third H Reactor E-N loading has recently become available for analysis. The buildup of product is much slower in fringe blanket material then in core target pieces. The s… more
Date: November 21, 1963
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
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Preliminary survey, Reactor formation of rhenium-tungsten alloy

Description: This document considers the costs of rhenium formation as produced by irradiating tungsten. Two isotopic compositions of tungsten are considered for the study. The cost for reactor-formed rhenium appears to be prohibitively high -- over $20 per gram. This cost would exist for tungsten containing 90% 186, 9, 184, and 1% tungsten 182 and 183. The cost of alloy made fro natural isotopic compositions of tungsten would be higher by a factor of 3, and would take prohibitively long to produce signific… more
Date: November 11, 1963
Creator: Lang, L. W. & Meichle, R. H.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: October 1963

Description: This report, for October 1963 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.
Date: November 21, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Summary report, Flexible VSR`s and VSR channel sleeve development programs

Description: (VSR = vertical safety rod.) This report summarizes results of development programs which have evaluated vertical rod channel sleeving materials and provided flexible vertical rods, acceptable for both interim use before rod channel sleeving, and for subsequent use in sleeved channels. B{sub 4}C is the rod material; graphite and Al oxide are among the sleeve materials.
Date: November 15, 1963
Creator: Kempf, F. J.
Partner: UNT Libraries Government Documents Department
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The reactivity evaluation of PITA-IP22 demonstration load, Supp. 3

Description: PITA-IP22, SUPP II has pointed out that distinct processing advantages may be realized by simplifying the E-N core by minimizing the number of different kinds of charges and the number of target slugs per charge. In an effort to experimentally verify the theoretical effects of converting to a simplified loading, a 102-tube test section, consisting of three 5.0 inch Li-Al target elements per tube was recently charged in H Reactor, under authority of the PITA supplement. The purpose of this docum… more
Date: November 18, 1963
Creator: Essig, T. H.
Partner: UNT Libraries Government Documents Department
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Reactor Physics monthly technical report, October 1963

Description: Progress is reported for the month of October, 1963 in the following research and development activities: Lattice parameter and spectral index experiments; T{sup 3} and Np{sup 237} production rates for a highly enriched fuel loading; graphite heat generation; technical bases; physics study of single tube fuel element; thirty-six tube special 1.25 w/o fuel test loading; and code development FLEX 3.
Date: November 1, 1963
Creator: Nichols, P. F.
Partner: UNT Libraries Government Documents Department
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Development status and incentives for the hot die sizing process

Description: The development status and incentives for the hot the sizing process for reactor production fuels is reviewed and updated and economic justification for the process for four different case studies presented. Based on whether the end bonding step can be eliminated, payout periods of 1.2 to 1.7 years can be realized if the present AlSi process (two-shift, five-day week) is converted to hot die sizing for all reactors. For K-Reactor operation only, Payouts of 1.5 to 2.2 years can be realized by co… more
Date: November 20, 1963
Creator: Blanton, W. A.
Partner: UNT Libraries Government Documents Department
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Suggested startup plan with high CO{sub 2}

Description: Following the startup of 11-6-63 at 105-B, there was an operating period where graphite stringer temperatures were above allowable, and a PCA was authorized for continued operation. It is probable that the combined effects of raising the CO{sub 2} rapidly along with the fast approach to full power level caused the temperature effects. The CO{sub 2} reached 67%. As an interim step, it is suggested that startup CO{sub 2} additions be tailored to level off at 5--10% below the equilibrium level, an… more
Date: November 12, 1963
Creator: Gross, P. D.
Partner: UNT Libraries Government Documents Department
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Interim report III, production test IP-560-A: Half-plant low dichromate, low pH water treatment at C Reactor

Description: A half-plant low dichromate-low pH test was started at C Reactor on March 1, 1963. The test will demonstrate whether l.0 ppm sodium dichromate provides adequate corrosion inhibition when,the reactor coolant pH is 6.6. The test monitoring will consist of ex-reactor tube examinations, in-reactor.wall thickness measurements, coupons, visual examination of fuel elements and fuel element weight loss measurements. Previous interim reports have discussed the results obtained from the visual examinatio… more
Date: November 7, 1963
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
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Physics study of Po{sup 210} production capabilities in N Reactor

Description: The production of Po{sup 210} by irradiating Bi{sup 209} has been proposed as a possible use of N Reactor. The purpose of this study was to make an estimate of the production rates for various exposure times and flux levels. The production rate was calculated for the three flux levels of: (1) 5.0 {times} 10{sup 13} neutrons/cm{sup 2}/second, which is about the average flux level expected in the N Reactor graphite moderator; (2) 6.74 {times} 10{sup 13} neutrons/cm{sup 2}/second, which is the est… more
Date: November 19, 1963
Creator: Dieterich, R. A.
Partner: UNT Libraries Government Documents Department
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