182 Matching Results

Search Results

Results: 1 - 24 next
open access

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, … more
Date: July 14, 1960
Creator: Adams, O. E. Jr.; Hedges, J. W. & Jones, S. S.
Partner: UNT Libraries Government Documents Department
open access

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 radia… more
Date: July 14, 1960
Creator: Albright, G. H.; LeDoux, J. C. & Mitchell, R. A.
Partner: UNT Libraries Government Documents Department
open access

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
open access

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
open access

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… more
Date: July 22, 1960
Creator: Barnes, R. H. & Sunderman, D. N.
Partner: UNT Libraries Government Documents Department
open access

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
open access

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
open access

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
open access

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 reac… more
Date: July 1, 1960
Creator: Beck, R. L.
Partner: UNT Libraries Government Documents Department
open access

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 … more
Date: July 20, 1960
Creator: Bennett, L. L. & Jaye, S.
Partner: UNT Libraries Government Documents Department
open access

Project CGC-830 Plant Modifications for Reprocessing Non-Production Reactor Fuels

Description: Facilities are to be designed for installation at Hanford for the reprocessing of irradiated, low enrichment fuels from non-production reactors, see Reference 1 and 2. The initial design of the processing facilities is to be based on processing the fuels discharged from the Dresden, Yankee, Piqua, Pathfinder and Shippingport (blanket elements only) reactors. Properties of the fuels and cladding make it impossible to completely process them in existing equipment, although the separation and deco… more
Date: July 29, 1960
Creator: Bierman, S. R.; Graf, W. A.; Kass, M.; Kligfield, G.; McKee, R.W.; Patridge, L. F. et al.
Partner: UNT Libraries Government Documents Department
open access

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
open access

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
open access

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 resist… more
Date: July 10, 1960
Creator: Blankenship, W. P.; Goodspeed, R. C.; Markley, R. A. & Mitchell, P. V.
Partner: UNT Libraries Government Documents Department
open access

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 throug… more
Date: July 6, 1960
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
open access

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… more
Date: July 28, 1960
Creator: Brown, G. D. & McConiga, M. W.
Partner: UNT Libraries Government Documents Department
open access

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 w… more
Date: July 12, 1960
Creator: Brown, K B
Partner: UNT Libraries Government Documents Department
open access

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
Back to Top of Screen