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Periodic Intercalibration of Temperature Sensing Elements, Core I, Seed I. Test Results T-641306

Description: BS>Intercalibration data for various temperature sensing elements in the reactor coolant system are obtained and compared with calculated source activity levels and observed channel levels. The readings of 20 of the 62 core thermocouples were either less than 400 deg F, which was off scale on the recorder, or were plus or minus 20 deg F from the calibrating resistance thermometer temperatures. The remainder of the readings were within plus or minus 3% of the temperatures of the calibrating ther… more
Date: October 24, 1960
Partner: UNT Libraries Government Documents Department
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A RESONANCE IN THE Lambda pi SYSTEM

Description: The authors report a study of the reaction K{sup -} + p {yields} {Lambda}{sup 0} + {pi}{sup +} + {pi}{sup -} produced by 1.15 Gev/c K{sup -} mesons and observed in the Lawrence Radiation Laboratory's 15-in. hydrogen bubble chamber. A preliminary report of these results was presented at the 1960 Rochester Conference. The beam was purified by two velocity spectrometers. A hyperon/observed during the run and the preliminary cross sections for various K{sup -} reactions at 1.15 Bev/c have been repo… more
Date: October 24, 1960
Creator: Alston, Margaret; Alvarez, Luis W.; Eberhard, Philippe & Wojcicki, Stanley G.
Partner: UNT Libraries Government Documents Department
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Stability of Phosphors to Beta Radiation

Description: From foreword: This report presents the results of a study on the stability of phosphors under high energy beta radiation.
Date: June 24, 1960
Creator: Senett, W. P.; Diehl, K. & Wright, R.
Partner: UNT Libraries Government Documents Department
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Magnetic Recorder for Nuclear Pulse Application : Covering the Period from December 6, 1959 to February 5, 1960

Description: "Abstract: An evaluation of a modulator flux sensitive playback head to be used with an analog magnetic recorder for nuclear pulse information storage was made. The modulator head was found unsultable. A pulse stretching unit was constructed which takes pulses from a standard linear pulse amplifier and provides an output signal suitable for driving a recording head."
Date: February 24, 1960
Creator: Burgwald, G. M.
Partner: UNT Libraries Government Documents Department
open access

Measurement of fuel element temperature changes as the result of film deposition, production test IP-314-A. Supplement E

Description: Irradiation of a third thermocouple train with a thermocouple element of the same design as used on the previous two trains, but with different heater elements, is authorized to an exposure no greater than 1000 MWD/T. A second decontamination of KER-1 using the same procedures as for the first decontamination is also authorized.
Date: October 24, 1960
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
open access

Alpha correlation

Description: This study was developed to provide a correlation for the evaluation of the pile C{sub RI}/Tube C{sub RI} ratio (alpha value) for each of the Hanford reactors.
Date: March 24, 1960
Creator: Cremer, B. R.
Partner: UNT Libraries Government Documents Department
open access

Redox Birch recovery scope design. Revision 1

Description: The scope design for Birch recovery at Redox was presented in September 12, 1960. Final plutonium purification and decontamination by anion exchange in a pulsed-bed contactor under development by Hanford Laboratories was proposed. Potential advantages of low cost and improved operability were anticipated from the new contactor; when these were not demonstrated in the development work in time to meet project schedules, it was decided to revert to the Higgins-type contactor for which considerable… more
Date: October 24, 1960
Creator: Hanthorn, H. E.
Partner: UNT Libraries Government Documents Department
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Hydraulic demand curves for standard BDF geometry at low tube powers

Description: Information concerning the pressure-flow relations in reactor process tubes at very low heat generation rates is of value for determining flow requirements during shutdown conditions. Since such information is quite difficult to calculate when boiling occurs, a brief laboratory investigation was conducted to obtain experimental data. The data obtained for BDF geometry are recorded in this report for distribution to those persons having an interest in the application of the results to reactor op… more
Date: March 24, 1960
Creator: Waters, E. D. & Fitzsimmons, D. E.
Partner: UNT Libraries Government Documents Department
open access

Piping Changes for Increased Production at B, D, DR, F, C and H Reactors calculations

Description: On January 22, 1960, HW-63487 Piping Changes for Increased Production at B, D, DR, F, C, and R Reactors, was published. This study investigates the valve pit piping, front and rear face piping,and effluent lines between the 105 Buildings,and the retention basins to determine modifications necessary to increase power levels in the 100-B, D, DR, F, C, and H Areas by increasing either or both temperatures and flows. The study was based on detailed hydraulic and stress calculations of the existing … more
Date: March 24, 1960
Creator: Bauer, G. H.; Harrison, C. W.; Hill, V. R.; McLenegan, D. W. & Mondt, J. F.
Partner: UNT Libraries Government Documents Department
open access

Artificial cooling of the Columbia River by dam regulation 1959

Description: An increase in the flow of water from the lower depths of the Grand Coulee Reservoir was used to lower the river temperature at Hanford Atomic Products Operation (HAPO). A net average daily reduction of over 1 C resulted. The average for one day varied from 1.7 to 0.2 C. Before the dam control period, the Bonneville Power Administration transferred load from Grand Coulee Dam to other dams in order to conserve cold water. The authors calculate that there was more value to HAPO from this transfer… more
Date: June 24, 1960
Creator: Kramer, H. A.
Partner: UNT Libraries Government Documents Department
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Enriched fuel element column charge length optimization

Description: Results of the study on the best charge length of enriched fuel to be used in the reactors Indicate that with the present quality of fuel elements there is no economic incentive to change the charge lengths from those currently being used. The expected returns for operating D and C reactors at optimum conditions with different length enriched fuel charges are given in figures. Detailed results from calculations concerning the other reactors would also exhibit similar trends.
Date: October 24, 1960
Creator: Blyckert, W. A.
Partner: UNT Libraries Government Documents Department
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Note on the Numerical Evaluation of Integrals of the Form [integral] [superscript infinity] [subscript infinity] f(x) [golden ratio constant] (x) dx, with Particular Reference to the Determiniation of the Expectation of a Function of a Normally Distributed Random Variable

Description: Abstract: A method is given for the rapid and accurate numerical integration of integrals of the form [integral] [superscript infinity] [subscript infinity] f(x) [golden ratio constant] (x) dx, where f(x) is "smooth."
Date: May 24, 1960
Partner: UNT Libraries Government Documents Department
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COMPARISON OF FEDAL MONITOR READINGS WITH RADIOCHEMICAL SAMPLE DATA. CORE I, SEED 1. Test Results T-641305

Description: Tests were conducted to compare the specific isotopic fission product activities with those of delayed neutron emitters which are monitored by the FEDAL System, and to obtain irformation on the source of activity observed in the PWR coolant. The monitors detected definite activity bursts of delayed neutrons during load increases, which indicated a rupture of the core blanket element. A radiochemical analysis of the coolant data did not show any unusual activity bursts, thus indicating a fuel el… more
Date: October 24, 1960
Partner: UNT Libraries Government Documents Department
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URANIUM RECOVERY FROM LAPRE-II FUEL SOLUTION BY TBP EXTRACTION

Description: A feed preparation and solvent extraction flowsheet was developed for the recovery and decontamination of highly enriched uranium from the LAPRE-II reactor fuel solution. The fuel solution, U(IV) in concentrated H/sub 3/PO/sup 4/ ' was dilutad, Fe(NO/sub 3/)/sub 3/ added to complex phosphate and supply salting strength, NaNO/sub 2/ added to oxidize U(IV) to U(VI) so that U may be extracted efficiently with 6% TBP. The flowsheet is designed for operation in noncritically safe equipment. (auth)
Date: June 24, 1960
Creator: Flanary, J R
Partner: UNT Libraries Government Documents Department
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Loading, Shipping and Testing Procedures for Task 2 Isotopic Powered Thermoelectric Generator. Preliminary Technical Manual

Description: A preliminary report on the operations and procedures for handling a 125- w thermoelectric generator and its isotopic heat source is presented. Full-scale mock-ups were used to develop the procedures. A cylindrical metal block of Inconel X will be remotely loaded with an isotope at ORNL. The block will then be sealed snd loaded into a specially designed cask and shipped by rail to the Martin nuclear hot cell facility, where the second phase of the operation will be conducted. (W.D.M.)
Date: March 24, 1960
Creator: Reilly, M. J.
Partner: UNT Libraries Government Documents Department
open access

MAGNETIC RECORDER FOR NUCLEAR PULSE APPLICATION. Period covered: December 6, 1959 to February 5, 1960

Description: An evaluation of a modulator flux sensitive playback head to be used with an analog magnetic recorder for nuclear pulse information storage was made. The modulator head was found unsultable. A pulse stretching unit was constructed which takes pulses from a standard linear pulse amplifier and provides an output signal suitable for driving a recording head. (For preceding period see ARF-1151- 3.) (C.J.G.)
Date: February 24, 1960
Creator: Burgwald, G.M. & Norton, R.M.
Partner: UNT Libraries Government Documents Department
open access

Radiological Implications Concerning the Use of Argon as the Core Cover Gas in Sodium Graphite Reactors

Description: The substitution of argon for helium as the inert core cover gas in sodium graphite reactors would result in an economic advantage in most areas of the world. The actual amount of extra radioactivity which would occur is calculated, and the radiological significance of this activity is evaluated with reference to existing design and operating characteristics of sodium graphite reactors. (W.D.M.)
Date: October 24, 1960
Creator: Hart, R. S.
Partner: UNT Libraries Government Documents Department
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Effects of Yttrium on the Fabrication and Tensile Properties of Two Modified Stainless Alloys

Description: Alloys containing 55 wt.% iron--22 wt.% nickel-- 17 wt.% chromium--2.5 wt.% molybdenum- 1.0 wt.% niobium-0.03 wt.% carbon-- 0.5 wt.% manganese-- 0.5 wt.% silicon with nominal additions of from 0 to 1.5 wt.% yttrium, and 36 wt.% iron-37 wt.% nickel--18 wt.% chromium--2.5 wt.% molvbdenum- 1.5 wt.% niobium-- 1.0 wt.% aluminum-0.05 wt.% carbon--0.5 wt.% manganese-- 0.5 wt.% silicon with nominal additions of from 0 to 2.0 wt.% yttrium, were prepared by vacuum- induction melting. Alloys containing 55… more
Date: February 24, 1960
Creator: DeMastry, J. A.; Shober, F. R. & Dickerson, R. F.
Partner: UNT Libraries Government Documents Department
open access

TRIBUTYL PHOSPHATE-HYDROCARBON DILUENT REPURIFICATION IN RADIOCHEMICAL PROCESSING AT ORNL: STATUS SUMMARY

Description: The need for, and the adequacy of, the sodium carbonate washing technique in chemical purification of tributyl phosphate-hydrocarbon extractant prior to its re-use in radiochemical processing was examined, primarily in terms of Ru, Zr, and Nb activities. Operating experience from ORNL Purex and Thorex Pilot Plants is compared with Hanford operations and upper limits for activities are suggested. Recommendations are made for development studies with the ORNL Power Reactor Fuel Processing Pilot P… more
Date: March 24, 1960
Creator: Davis, W. Jr.
Partner: UNT Libraries Government Documents Department
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Crystallography of Some of the Transition Element Beryllides

Description: A crystallographic study of the transition element beryllides was undertaken in support of phase diagram work. These beryllides are very high melting, and the use of ordinary methods make it difficult to determine stoichiometry. We have succeeded in establishing the compositions and complete crystal structure description of all of the room temperature stable or metastable compounds of the beryllides of niobium, tantalum, titanium zirconium, hafnium, vanadium, chromium and molybdenum. Since some… more
Date: May 24, 1960
Creator: Zalkin, Allan, 1926- & Sands, Donald, 1929-
Partner: UNT Libraries Government Documents Department
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