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Single tube meltdown incident

Description: In connection with design of rear face fittings for the plant-expansion study currently being conducted we have been asked to determine if rear face pressurization is required for safety reasons and if so, how much. Pressurization of the rear face piping would be used to provide sufficient reverse flow to prevent process tube burnout in the event of complete loss of coolant supply to a single tube by virtus of a front connector failure. Consideration of the effectiveness of rear face pressurization, however, requires a more general look at the problem of single tube meltdown than that provided by considering front fitting failure alone.
Date: February 1, 1960
Creator: Trumble, R. E.
Partner: UNT Libraries Government Documents Department
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EN-318 evaluation of slow warm-up through special test of MC-890 type power supplies

Description: ESE-171: This EN run was made to determine if there is any relationship between the H-5 transistor electrical characteristics, the assembly processes, and slow warm-up of the MC-890 Power Supply. Included is the test data on the H-5 transistors and the results of the High Temperature Life Test (185 {degrees}F) of 380 MC-890 Power Supplies.
Date: September 1, 1960
Creator: Ling, R.F.
Partner: UNT Libraries Government Documents Department
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Cathode brazing control for GEXF

Description: As a result of repeated epidemic losses of brazed cathodes at GEXF, the engineering work necessary to determine the best brazing cycle and the controls necessary to insure reproducibility and high yields in the future was carried out by means of EN-297. Included are the procedures used and the tests made to verify the conclusions drawn and the recommendations made.
Date: March 8, 1960
Creator: Thinnes, E.L.
Partner: UNT Libraries Government Documents Department
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Qualification Approval Tests on resistance products Co.`s type {open_quotes}H{close_quotes} Carbon Composition resistors (0.2 and 40 Megohm)

Description: Engineering Work Requests ESE-48 & 49 established a program for performance of Qualification Approval Tests on RPC`s 0.2 and 40 meghom Carbon Composition Resistors. This report is an accounting of these tests wherein (50) samples of each component were subjected to QA tests per drawings 8O2C250 and 802C251. Tests are explained and results tabulated.
Date: March 25, 1960
Creator: Dixon, L.W.
Partner: UNT Libraries Government Documents Department
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Graphite burnout, interim report on IP-25-A (PT-105-532-E)

Description: Graphite reacts with such gases as CO{sub 2}, O{sub 2}, or water vapor to form gaseous oxides of carbon. In the case of CO{sub 2}-graphite interaction, the reaction rate is not significant until about 550 C. Water oxidizes graphite, very roughly, three times faster than CO{sub 2}. Air will oxidize graphite appreciably at temperatures below 500 C. Graphite removal from Hanford reactors is very important, since graphite is used both as a structural support and a moderator for neutrons. Griggs has shown that small graphite samples oxidized to 10 per cent weight loss had only about one-half their original compression strength. Hence, the longevity of the reactors depends to a great extent on maintaining a low graphite oxidation rate. A means of monitoring the extent of graphite loss, i. e., the burnout rate, is necessary to establish future reactor operational standards. Presently, weighed samples of reactor grade graphite are placed along the length of an empty process channel in each reactor. Thus, a sample is exposed to the reactor`s ambient conditions of power level, moderator temperature, and gas composition. This program was initiated in the vicinity of June, 1953 by Woodley. This report presents data on graphite burnout obtained from in-reactor experiments authorized under IP-25-A (PT-105-532-E) from August, 1957 to January, 1960. Burnout rates are obtained by a direct measurement of the weight loss of control graphite samples exposed to the reactor atmosphere.
Date: March 15, 1960
Creator: Ryan, B. A. & de Halas, D. R.
Partner: UNT Libraries Government Documents Department
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EEN-307, Irradiation of units at low temperature test

Description: EWR-ESE-144, Fifty MC-890 type final assemblies were subjected to irradiation at low temperature test in order to determine if irradiation would reduce the frequency of high voltage breakdowns. A control lot of a like number of units was subjected to low temperature test in the same manner except without irradiation.
Date: April 13, 1960
Creator: Guthrie, J.B.
Partner: UNT Libraries Government Documents Department
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EEN-333, revised getter flash procedure

Description: EWR No. VTE-188--Tubes processed by flashing getters immediately prior to seal-off from vacuum systems are compared for total residual gas pressure to tubes processed by flashing getters after tubes were sealed off vacuum systems. Comparisons of residual pressures determined from current flows in the cold cathode ion gauge.
Date: June 28, 1960
Creator: Brown, W.C.
Partner: UNT Libraries Government Documents Department
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Radiations from nuclear weapons - signal detectors - NASA program information

Description: This letter is for the purpose of supplying the information that you requested at the meeting of the sub-committee on Project Vela. It is divided into three parts: (1) Radiations from nuclear weapons; (2) Backgrounds for Vela Signal Detectors; (3) Discussion of the NASA program.
Date: February 10, 1960
Creator: White, R. S.
Partner: UNT Libraries Government Documents Department
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LRL background measurements program for ICBM discrimination

Description: Several proposals have been made for discriminating between Intercontinental Ballistic Missiles (ICBM) and decoys. Primary fundamental particles or high energy electromagnetic radiation can be scattered from or can activate the targets. The secondary radiation is observed by directional detectors that are positioned close-by and the information is transmitted to control centers on the ground. Lawrence Livermore Laboratory proposes a program for measurements of the natural space radiations. Eventually, the space backgrounds must be measured before a satisfactory discrimination system can be perfected. Past and scheduled background measurements are described and a measurement program is proposed.
Date: March 9, 1960
Partner: UNT Libraries Government Documents Department
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909B high energy gull generator

Description: No Description Available.
Date: December 31, 1960
Creator: Stephens, W. H.
Partner: UNT Libraries Government Documents Department
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Report on 8-inch isostatic press explosion at Site 300

Description: On 3 March 1960 at 11:30 a.m. a detonation occurred in the 8-inch isostatic press. The press and building were completely destroyed. Operating personnel were protected and no injuries resulted. Adjacent facilities were not affected. The press was housed in a temporary facility located in the southwest portion of Section 26, Site 300. The facility was situated approximately 1000 feet west of the main site road, and 1400 feet north of the county road. The press building was of frangible wood construction and was surrounded by an earth barricade. A remote control building, provided with overhead protection, a mechanical equipment room, and a transportainer magazine were located outside the barricaded press building.
Date: April 6, 1960
Partner: UNT Libraries Government Documents Department
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SRP radioactive waste releases. Startup through 1959

Description: This report summarizes and documents radioactive waste released to the environs of the Savannah River Plant from startup through 1959. During this period, the quantity of beta-emitting radioisotopes released was determined by a total or ``gross`` analysis. However, advanced instrumentation and technology now permit an economical determination of most individual radionuclides. Therefore, future waste audit reports, beginning with January 1960, will record the quantity of specific radioisotopes released rather than gross amounts.
Date: September 1, 1960
Creator: Ashley, C.
Partner: UNT Libraries Government Documents Department
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Evaluation of reduction of I.D. defects in I and E tubing with various billet I.D.: Experiment Number U-11

Description: It has been thoroughly documented in previous Bridgeport Brass Company reports that a problem exists in the production of HAPO I and E ``O`` size slugs via the extrusion route due to an excessive number of rejects for I.D. seams. As a result of a previous short-run experiments, it was suggested that smaller I.D. billets be employed, thus reducing the reduction ratio on the I.D. It was thought that this factor may contribute to the seam formation in the extreme flow demanded of the metal. It was also thought that the long billets, half of an ingot, could contribute to this defect. Therefore in this extrusion, some short billets, one-third of an ingot, were employed. Other methods or techniques for reducing the incidence of this I.D. defect will be studied later. It was intended to limit the present experiment to a study of the potential reduction involved in the above; namely, billet length and billet I.D., in an extrusion experiment with sufficiently large quantity of billets to give a fairly large number of slugs. By proper design, other contributors to the defect were held constant or randomized. This experiment proved definitely that a reduction in I.D. rejects due to seams and mechanical causes could be effected by a reduction in billet I.D. A conclusive result showed the 1 5/8 I.D. billet to produce the least extruded I.D. rejects. It was also found that extruded I.D.`s of less than .340 inch would improve the I.D. surface quality; that is, the incidence of the I.D. seam rejects. In this production run, a new method of packaging the I and E extruded rods resulted in receipt of rods at MCW with superior straightness. Therefore, the method of packaging for shipment in steel pans will be discontinued in the future.
Date: July 21, 1960
Creator: Puterbaugh, J. F.
Partner: UNT Libraries Government Documents Department
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Appendix 8, Decay of Cerium-144

Description: As part of an earlier program of investigation in this laboratory, studies were made of the gamma ray spectrum and the beta ray spectrum of cerium-144. In the present work, seme coincidence studies were made on one of the beta groups appearing in the cerium-144 decay and on the gamma rays appearing in the deexcitations from the energy levels of praseodymium-144. Sources of cerium-144 were prepared frcm carrier free radioactive cerium-144 as supplied by the Oak Ridge National Laboratory. The sample material was more than two years old at the time of preparation of sources. No additional chemical purification was attempted. Sources for use in the beta crystal spectrometer were mounted on thin Formvar film on spectrometer ring mounts. The gamma ray spectrum of cerium-144 in the energy range 20 kev to 180 kev is shown in Figure 1. This spectrum was determined using a 2-inch by 2-inch NaI(Tl) crystal. The pulse spectrum was analyzed by a Radiation Instrument Development Laboratory (RIDL) 200 channel analyzer. The spectrum gives clear evidence of gamma ray peaks at 34 {+-} 3 kev and 134 {+-} 2 kev. A rather broad peak at 80 kev is observed. An indication of a gamma ray group of energy near 100 kev is also shown. The resolution of the detecting assembly was 9.8 percent at 662 kev. The uncorrected relative intensities of the three groups of 34, 80 and 134 kev are 95, 35, and 100, respectively. These intensities are for the gamma radiation exclusive of internal conversion. Gamma-gamma coincidence measurements were made using two of the 2-inch by 2-inch sodium iodide crystals placed at 90 degrees to one another, Ganmma radiation of a particular energy was selected by means of a single channel analyzer and the 200 channel analyzer was used to analyze any coincident pulses …
Date: June 1, 1960
Creator: Sathoff, H. J. & Azuma, T.
Partner: UNT Libraries Government Documents Department
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AUEOUS CORROSION OF ALUMINUM AT 260 C

Description: Ten experimental alloys of aluminum containing up to 4% nickel corroded uniformly, without intergranular attack, when exposed for 3 months to flowing deionized water at 260 deg C. The average penetration rates were between 1.4 and 1.9 mils per month. (auth)
Date: October 1, 1960
Creator: Whatley, V.
Partner: UNT Libraries Government Documents Department
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