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Development test IP-342-AG increase of bulk outlet water temperature 105-DR

Description: The objective of this test is to determine the DR-Reactor effluent systems characteristics under 95 degrees Celsius bulk temperature operation. This proposed bulk temperature increase from 93.5 to 95 degrees represents a 33% decrease in the bulk temperature suppression below the boiling point. A major aim of this test will be to evaluate the degree of increased maintenance at this higher temperature operation. The basis and justification, test preparation and instrumentation, procedure, costs, outage time, hazards, standards, and responsibilities are discussed in this document.
Date: July 14, 1960
Creator: Adams, O. E. Jr.; Hedges, J. W. & Jones, S. S.
Partner: UNT Libraries Government Documents Department
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Evaluation of Buried Conduits as Personnel Shelters

Description: Supersedes ITR-1421. Twelve large-diameter buried conduit sections of various shapes were tested in the 60- to l49-psi overpressure region of Burst Priscilla to make an empirical determination of the degree of personnel protection afforded by commercially available steel and concrete conduits at depths of burial of 5, 7.5, and 10 feet below grade. Essentially, it was desired to assure that Repartment of Defense Class I, 100psi and comparable radiations, and Class II, 50-psi and comparable radiations, protection is afforded by use of such conduits of various configurations. Measurements were made of free-field overpressure at the ground surface above the structure; pressure inside the structures; acceleration of each structure; deflection of each structure; dust inside each structure; fragmentary missiles inside the concrete structures; and gamma and neutron radiation dose inside each structure. All buried conduit sections tested provided adequate Class I protection for the conditions under which the conduits were tested. Standard 8-foot concrete sewer pipe withstood 126-psi overpressure without significant damage, minor tension cracks observed; standard 10-gage corrugated-steel 8-foot circular conduit sections withstood 126- psi overpressure without significant damage; and standard 10-gage corrugated- steel cattle-pass conduits withstood 149-psi overpressure without significant damage. Durations of positive pressure were from 206 to 333 milliseconds. (auth)
Date: July 14, 1960
Creator: Albright, G. H.; LeDoux, J. C. & Mitchell, R. A.
Partner: UNT Libraries Government Documents Department
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LEAKAGE OF WATER FROM GASKETED JOINTS PROPOSED FOR THE HWCTR. PART I

Description: When mockups of typical gasketed joints proposed for the HWCTR were subjected to thermal and pressure cycling that simulated reactor operating conditions, the average leakage rate was less than 0.11 lb of water per year per linear inch of gasket. The joints were exposed to deionized light water and were cycled 100 times from about 70 deg C and atmospheric pressure to 250 deg C and 1000 psig. (auth)
Date: July 1, 1960
Creator: Apple, F.C.
Partner: UNT Libraries Government Documents Department
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PRELIMINARY HAZARDS EVALUATION OF THE ISOLATED COOLANT LOOPS IN THE HWCTR

Description: The design features of two isolated coolant loops in the Heavy Water Components Test Reactor (HWCTR) and the effect of these features on reactor safety are described. It is shown that limitations on the operating conditions, backed up by properly chosen safety systems, will permit operation of the loops without adding appreciably to the reactor hazards. (auth)
Date: July 1, 1960
Creator: Arnett, L.M.; Parkinson, T.F.; Randall, D. & Ross, C.P.
Partner: UNT Libraries Government Documents Department
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Apparatus for the Study of Fission-Gas Release From Fuels During Postirradiation Heating at Temperatures Up to 1600 C

Description: An apparatus to study rare-gas fission-product release from nuclear fuel materials during postirradiation heating was developed. Xenon and krypton fission gases escaping from a small specimen during heating at constant temperature are measured using a continuous radioactivity monitor and charcoal adsorption traps. The rhodium-wound furnace is capable of operation at 1600 deg C. Helium carrier gas is purified by activated alumina, copper, and zirconium traps, and the oxygen and moisture contents of the gas are monitored continuously. The operating procedure and data are presented for a typical heating experiment in which fused uranium dioxide was studied. (auth)
Date: July 22, 1960
Creator: Barnes, R. H. & Sunderman, D. N.
Partner: UNT Libraries Government Documents Department
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Consolidated Edision Thorium Reactor Physics Design

Description: The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and power density distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor.
Date: July 1960
Creator: Barringer, H. S.; Flickinger, R. B. & Spetz, S. W.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Critical Experiments With Oxide Fuel Pins

Description: Critical experiments with pin-type oxide fuel elements for the CETR are described. These experiments were conducted to provide data on the infinite medium properties of the lattice inside the canned elements in the various CETR loading zones and to obtain specific information on the fullsize CETR core. Measurements are described and results are interpreted. (J.R.D.)
Date: July 1, 1960
Creator: Batch, M. L. & Snidow, N. L.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Critical Experiments with Oxide Fuel Pins

Description: This report describes the critical experiments with pin-type oxide fuel elements for the Consolidated Edison Thorium Reactor (CETR). This report also describes the measurements and gives a brief interpretation of the results in some cases
Date: July 1960
Creator: Batch, M. L. & Snidow, N. L.
Partner: UNT Libraries Government Documents Department
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Reactor Materials Study. Research and Development of Metal Hydrides. Quarterly Report No. 7 for April 1, 1960 to June 30, 1960

Description: High-temperature x-ray diffraction experiments provided confirming evidence regarding the origin of the metastable gamma phase and of the general features of the zirconiumhydrogen phase system. These experiments also showed that the reaction alpha + delta -- beta (the eutectoid reactlon on heating) proceeds at an extraordinarily slow rate, although the reverse reaction proceeds so rapidly that beta phase cannot be retained to room temperature by quenching. The sluggishness of the eutectoid reaction on heating undoubtedly resulted in erroneous interpretation of certain physical and mechanical properties determined of the mechanical properties of zirconium hydride containing various minor alloy additions is continuing. Although these data are still quite sketchy, alloy additions of 5 at.% Sc or 2.2 at.% Cu show the most promise at this time. (auth)
Date: July 1, 1960
Creator: Beck, R. L.
Partner: UNT Libraries Government Documents Department
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Pressure Rise in the Reversed Flow HRT Following a Cold Fluid Accident During Startup

Description: The maximum pressure rise in the core of the Homogeneous Reactor Test following a cold water accident during startup was calculated for upward flow of core fluid and for reversed flow. With the reactor initially critical at 260 tained C and a power level of 0.04 w, fuel solution at 100 tained C wse considered to enter the core at a flow rate of 150 gpm. With reversed flow this added reactivity at sn average rate of 1.7% o degradation t k/sub e// sec, while with upward flow the rate was 0.67% o degradation t k/sub e//sec. The core pressure incressed rapidly to a maxi-mum of 550 psi above normal operating pressure with reversed flow and 400 psi with upward flow when only the core pressurizer was available for fluid expansion. With the core and blanket pressurizers connected, the excess pressures were 375 and 210 psi, respectively. (auth)
Date: July 20, 1960
Creator: Bennett, L. L. & Jaye, S.
Partner: UNT Libraries Government Documents Department
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Spectrophotometric studies of solutions at elevated temperatures and pressures: status and program for FY1961 and part of FY 1962

Description: A program was initiated on the spectrophotometric study of aqueous solution chemistry. The goal is operation at temperatures up to at least 330 deg C and at pressures up to 200 atm, and to near the critical point if this appears to be feasible. A spectrometer capable of operation under these extreme conditions is being designed. (W.L.H.)
Date: July 19, 1960
Creator: Biggers, R. E. & Chilton, J. M.
Partner: UNT Libraries Government Documents Department
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Solid State Division Semiannual Progress Report For Period Ending February 28, 1955

Description: This semiannual progress report and future reports will be published as two documents to permit a wider distribution of the unclassified material. The report numbers are assigned in sequence so that the two reports will fall together when filed by report number.
Date: July 12, 1960
Creator: Billington, D. S. & Crawford, J. H., Jr.
Partner: UNT Libraries Government Documents Department
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Thermoelectric Nuclear Fuel Element Quarterly Progress Report for April- June 1960

Description: A hot-pressing system was designed and is adaptable for bomb melting experiments up to 2000 deg C. Two devices were constructed for measuring. One was designed to measure Seebeck coefficients, resistivities, and bond resistances of swaged and machined thermoelectric wafers and the other was designed to measure thermoelectric parameters of cylindrical thermoelectric pellets up to 1000 deg C. Design studies on a fission-fired thermoelectric generator were completed. Seebeck coefficient and resistivity were determined for Li/sub .06/Ni/ sub .94/ and p type PbTe as a function of thermal fiux at 400 deg C (average). Designs of prototype thermonuclear fuel elements are presented which include single-leg, double-leg, multi-junction notched-bar, and multi-junction pelletized designs. The effects of heattreatment on the thermoelectric properties of n and p type PbTe were determined at 68 deg F. The compatibility of PbTe and GeTe with cladding materials was investigated at 510, 600, and 650 deg C. The results of life testing a swaged single-leg GeTe element are discussed. The nuclear characteristics of a 500-kw thermoelectric core that employs a rod-type fuel element were calculated. Designs of a thermoelectric reactor system that utilizes thermal circulation are presented. (For preceding period see WCAP- 1545.) (C.J.G.)
Date: July 10, 1960
Creator: Blankenship, W. P.; Goodspeed, R. C.; Markley, R. A. & Mitchell, P. V.
Partner: UNT Libraries Government Documents Department
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Variable goal exposure plans for production type fuel elements

Description: The purpose of this memorandum is to transmit revisions to the goal exposure plans of reference (1). The plans, herein, supersede the previous recommendations. Similar to the plans of reference (1), the exposures calculated from these plans are designed to maximize plant return on the basis that the only restraint on metal usage is that imposed by the economics of the plutonium production process and associated uranium cycle, as described and defined in references (2) and (3). When metal throughput is limited by ex-reactor physical capabilities to a level lower than the unrestrained requirements, exposures higher than those recommended in this document would be indicated, as explained in reference (4). In essence then, these plans represent minimum economical exposures for current production fuel types, on the basis of attempting to maximize plant returns. The adjustments recommended herein, stem solely from revised estimates of the metal performance level indices (C{sub R} values) of the various metal types.
Date: July 6, 1960
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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Inventory radioactive liquid waste to ground 200 Areas, 1945--1959

Description: Since startup in January 1945 through December 1959, 4 {times} 10{sup 9} gallons of radioactive liquid wastes have been discharged to cribs and trenches at HAPO by the Chemical Processing Department facilities in the 200 Areas. These wastes contained approximately 2.5 {times} 10{sup 6} curies of beta emitters. The Scavenged Waste Recovery Program was completed in 1957 and Redox Plant process changes were made during the latter part of 1958. These changes resulted in significant reduction in the amount of radioactive materials that have been discharged to the ground in subsequent years, from a maximum of 8.2 {times} 10{sup 5} curies in 1955 to 9 {times} 10{sup 3} curies in 1959. Although these large amounts of radioactive materials have been discharged to the ground, periodic waste report inventories include no reduction due to radioactive decay. The estimated depletion by radioactive decay is the basis of this report.
Date: July 28, 1960
Creator: Brown, G. D. & McConiga, M. W.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section C Progress Report for April-May 1960

Description: An economical process was successfully demonstrated in bench-scale continuous equipment for stripping U from amines with ammonium carbonate solution. A continuous countercurrent mixer-settler extraction system was set up for further testing of the process for recovery of Te, Np, and U by tertiary amine extraction from UF/sub 6/ transfer cylinder was solutions. The effect of Purex aqueous feed adjustment procedures on Pu extraction by 1 M di-secbutyl phenylphosphonate (DSBPP) was studied. Work was continued on plutonium(IV) nitrate extraction with TBP and phenylphosphonate esters. The response of Ru/sup 106/ extraction to variations in the treatment of TBP-Amsco 125-82 solvent was tested. Two solvents have shown ability to extract cesium. (For preceding period see CF-80-3-136.) (W.L.H.)
Date: July 12, 1960
Creator: Brown, K B
Partner: UNT Libraries Government Documents Department
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Introduction to Electronic Analogue Computing

Description: The design, operation, applications, limitations, and programming of an electronic analog computer are described. (C.J.G.)
Date: July 1, 1960
Creator: Bryant, L. T.; Just, L. C. & Pawlicki, G. S.
Partner: UNT Libraries Government Documents Department
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Cost Study of a 100-Mw(E) Direct-Cycle Boiling Water Reactor Plant

Description: A technical and economic evaluation is presented of a direct-cycle light- water boiling reactor designed for natural circulation and internal steam-water separation. The reference lOO-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. (W.D.M.)
Date: July 1, 1960
Creator: Bullinger, C. F. & Harrer, J. M.
Partner: UNT Libraries Government Documents Department
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