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0-2 kv Flash Tube Supplies
The power supplies designed and constructed to power high-intensity flash tubes are described. Three supplies, capable of charging 100 mfd to 2 kv with a repetltion rate of not less than 0.8 sec, are operated remotely from a control panel containing 3 powerstats. The power supplies are full wave center trapped rectifiers employing silicon rectifiers. (M.C.G.)
Date:
March 15, 1962
Creator:
Miller, D. M.
Object Type:
Report
System:
The UNT Digital Library
0-2 kv Flash Tube Supplies
In order to perform the various experiments with a bubble chamber, a high intensity flash tube is used. This report briefly describes the power supplies designed and constructed to power these lamps.
Date:
March 15, 1962
Creator:
Miller, D. M.
Object Type:
Report
System:
The UNT Digital Library
6 kv CAPACITOR CHARGING SUPPLY
The power supplies designed and constructed to power high intensity flash tubes used in bubble chamber experiments are briefly described and are accompanied by a schematic diagram of the layout. (D.C.W.)
Date:
March 15, 1962
Creator:
Miller, D. M.
Object Type:
Report
System:
The UNT Digital Library
6 kv Capacitor Charging Supply
The power supplies designed and constructed to power high intensity flash tubes used in bubble chamber experiments are briefly described and are accompanied by a schematic diagram of the layout. (D.C.W.)
Date:
March 15, 1962
Creator:
Miller, D. M.
Object Type:
Report
System:
The UNT Digital Library
20-ton HE Cratering Experiments in Desert Alluvium: Final Report, May 1962
From abstract and summary: Project Stagecoach consisted of the detonation of three 40,000-pound charges. Blocks of cast TNT were stacked to resemble a sphere and, the whole center-detonated.
Date:
March 1960
Creator:
Vortman, Luke J. & MacDougall, H. R.
Object Type:
Report
System:
The UNT Digital Library
100-N Decontamination Facility Design Guide.
Space has been reserved near the southeast corner of the 100-N Area for the 122-N Decontamination Facility. Previous correspondence between Burns and Roe, Inc and General Electric bae discussed various facilities which might be needed in the building. The concepts of the decontamination processes are under active development by research groups at Hanford. At present, there are several workable processes known; each one has one or more fairly serious drawbacks.
Date:
March 8, 1960
Creator:
Bainard, W. D.
Object Type:
Report
System:
The UNT Digital Library
105-C overboring thirteen tube outage, March 6, 1961--March 10, 1961
C Reactor was shut down on a scheduled basis at 8:30 a.m. March 6, 1961 for the purpose of overboring 17 process channels. this report will cover that outage and discuss problems encountered in completing the tasks involved in overboring.
Date:
March 24, 1961
Creator:
Munro, C. A.
Object Type:
Report
System:
The UNT Digital Library
I-131 in milk from Cabriolet fallout
None
Date:
March 31, 1966
Creator:
Tamplin, A.
Object Type:
Report
System:
The UNT Digital Library
A 200-Watt Conduction-Cooled Reactor Power Supply for Space Application
The limited supply of relatively long-half-life isotopes having a reasonably high power density and the low conversion efficiencies obtainable with thermoelectric devices have so far limited the power output of isotope-fueled sources of electric power to several tens of watts. In addition, the high cost of the available isotopes results in a very large expense for isotope-fueled generators producing several hundred watts. It appears that a small, minimumweight, conduction-cooled reactor is an attractive alternate to the isotope-fueled power supplies in the 200-w size range. The proposed reactor is a small, high-density fast core of U/sup 233/ surrounded by a beryllium reflector. This approach, generally speaking, gives a reactor that is more compact and of lighter weight than can be obtained with a moderated system having a softer neutron spectrum. In the reactor design, the path of heat flow is from the core to the inner reflector and then to the thermoelements in close contact with the inner reflector. The reject heat flowing from the thermoelement cold junctions enters the outer pontion of the reflector, which acts as the heat sink and conducts the reject heat to the large, circular, tapered-fin radiator which is attached to the reflector. Survey physics calculations …
Date:
March 1, 1963
Creator:
MacFarlane, D. R.
Object Type:
Report
System:
The UNT Digital Library
500-Thgc--a 500 Node Transient Heat Transfer Code
This document is a user manual for those who are familiar with problems 500 Node Transient Heat Transfer Code.
Date:
March 27, 1964
Creator:
Blaine, R. A. & Berland, R. F.
Object Type:
Report
System:
The UNT Digital Library
710 reactor program, progress report No. 13
Declassified 4 Sep 1973. Information on the development of the 710 Reactor is presented concerning the performance testing of refractory-metal fuel elements, critical experiment mockup of 710 Reactor, reactor component design and development, and test facilities and pilot loop design, (DCC)
Date:
March 31, 1965
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
A 1000 HOUR TEST OF A CORROSION PRODUCT SEPARATOR UNIT IN A HAYNES ALLOY NO. 25 LOOP CONTAINING MERCURY--TEST G-16
One of the major unsolved problems affecting the life of the SNAP II Power Conversion System is the mass transfer of corrosion products by mercury and subsequent deposition. It is feared that the corrosion products might tend to accumulate in critical areas such as orifices, bearings and so forth. Therefore, this test was conducted to evaluate a corrosion product separator and to determine the influence of corrosion product removal on corrosion rate. The corrosion product separator was successful in removing 85 percent of the elements corroded from the container walls. The loop and separator, both fabricated from Haynes alloy No. 25, operated for 1000 hours. The mercury was boiled and condensed at 1100 deg F, superheated to 1190 deg F and subcooled to 325 deg F. The flow rate in this loop was much higher than in previous loops, being approximately 37 pounds of mercury per hour as contrasted with approximately l2 pounds of raercury per hour. No increase in corrosion rate was noticed as a result of the higher flow rates and velocity or by the removal of corrosion products. If this type of separator or an improved type works equally as well in the final application, the danger …
Date:
March 1, 1962
Creator:
Nejedlik, James F.
Object Type:
Report
System:
The UNT Digital Library
1000 Mwe Closed Cycle Water Reactor Study
This report has two volumes, volume 1 contains the summary and detailed description of plant design, volume 2 contains a comprehensive nuclear evaluation of the reactor core.
Date:
March 1, 1963
Creator:
Westinghouse Electric Corp., Pittsburgh, Pa. Atomic Power Div.
Object Type:
Report
System:
The UNT Digital Library
1000 MWE Closed Cycle Water Reactor Study Volume II
This report includes the nuclear evaluation that has been conducted for the purpse of studying those problem areas which are expected to increase in severity as the core size is increased to produce 1000 MWE.
Date:
March 1, 1963
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
14CO2 INCORPORATION INTO THE NUCLEIC ACIDS OF SYNCHRONOUSLYGROWING CHLORELLA CELLS
A study of the incorporation of {sup 14}CO{sub 2} into cell components of synchronously growing Chlorella pyrenoidosa has shown that DNA is synthesized primarily during the latter stages of the cell cycle prior to cell division. RNA was synthesized at an approximately equal rate during each of the three phases of the cell growth studied. No major differences were noted in the incorporation of {sup 14}CO{sub 2} into the soluble cell components in these long-term incorporation studies.
Date:
March 8, 1962
Creator:
Stange, Luise; Kirk, Martha; Bennett, Edward L. & Calvin, M.
Object Type:
Report
System:
The UNT Digital Library
2000 KILOWATT SODIUM TEST FACILITY. Project Description and Progress Reports, June 30, 1958 through September 30, 1959
The design and construction work completed on the 2000-kw Sodium Teat Facility during the period from April 1958 to Oct. 1959 is described. The purpose of the facility project in to test models of equipment components which are to be used in a moltsn plutonium, sodiumcooled fast reactor. (D. L.C.)
Date:
March 1, 1961
Creator:
Whinery, L.A.
Object Type:
Report
System:
The UNT Digital Library
The 4K ANGIE Code
The ANGIE, one of a series of reactor neutronic programs for an IBM 709 or 7090 data processing system, solves the time-dependent, multi-group, neutron diffusion equation for 1 to 26 energy groups applied to a rectangular mesh superimposed on either an x-y or an r-z plane.
Date:
March 5, 1962
Creator:
Stone, Stuart P.
Object Type:
Report
System:
The UNT Digital Library
630A MARITIME NUCLEAR STEAM GENERATOR. Progress Report No. 7
This progress report covers the period from November 15, 1963 to February 15, 1964. A study indicated that the most desirable type of blower drive turbine is one using main turbine throttie steam conditions and exhausting to the main turbine cross-over line. Preliminary planning for the initiation of a dynamic structural analyses of the overall steam generator was completed. External pressure loading and thermal stress calculations show that the calandria has a suitable design margin. A revised fuel latch operable from the rear face of the core was designed. A study was initiated to determine the feasibility of substituting Zircaloy for the stainless steel tubing within the active core. Preliminary sizing of control rod extensions and gang plates was completed. Initial loading of the second configuration of the 630A critical experiment reactor was completed. Detailed power distributions were measured in the 11 typical positions. Subcritical and critical rod worth curves were obtained in the critical experiment with up to 132 shim rods in the core. Moderator temperature coefficient measurements were made and agreed well with analytical data. Critical experiment correlation of fine radial power calculations in the revised mock-up showed good agreement. Performance specifications were prepared for a 1-Mw(e) power …
Date:
March 16, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
ABRAC--AN IBM-704 THREE DIMENSIONAL NUCLEAR-THERMAL DEPLETION PROGRAM WITH DISTRIBUTED VOID EFFECTS
ABRAC is a three dimensional nuclear thermal depletion program to study the effects of water moderator density changes, resulting from flow variations and boiling, on neutron flux distribution and depletion. The program requires an IBM-704 with a memory of 32.768 words and ten tape units. (auth)
Date:
March 1, 1960
Creator:
Jacobi, W. M.; Lawton, T. J.; Meanor, S. H. & Parrette, J. R.
Object Type:
Report
System:
The UNT Digital Library
THE ABSOLUTE ABUNDANCE OF THE CHROMIUM ISOTOPES IN SOME SECONDARY MINERALS
Isotopic assays have been made on the Cr in samples from 14 different chrominiferous minerals from different geographic and meteoritic sources. The results of the assays indicate that it is not possible to state unequivocally that variations in isotopic composition have been observed. (auth)
Date:
March 14, 1962
Creator:
Svec, H. J.; Flesch, G. D. & Capellen, J.
Object Type:
Report
System:
The UNT Digital Library
Abstract -- A description of low temperature hydriding of zircaloy at Hanford
The two K Reactors at the Hanford Plant of the Atomic Energy Commission were retubed in 1963 with ribless Zircaloy process tubes. These tubes, 1.81 inch OD x 0.037 inch wall, were made by tube reducing methods from extruded blooms and were installed without final pickling or autoclaving. These tubes are used with once-through filtered water with a maximum coolant temperature of approximately 110 C. After approximately two years` service, it was discovered that these tubes were absorbing hydrogen in a totally unexpected and alarming manner. It was found that the downstream few feet of these tubes had a layer of massive hydride platelets, several mils thick, on the inner surface, and that the hydrogen content of the tube wall beneath this layer had increased from the as-fabricated level of 5--15 ppm to 50--75 ppm. The portion of the tubes so affected was downstream of the fuel charge. Physical testing has indicated loss of ductility but no significant changes in strength, Cold burst tests resulted in a ductile failure mode with no tendency toward brittle fracture. A program to determine the basic mechanism responsible for this phenomenon as well as practical means for its elimination will be the subject of …
Date:
March 31, 1966
Creator:
Alexander, W. K.
Object Type:
Report
System:
The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; Ninth Quarterly Progress Report, (December 1963 - February 1964)
The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date:
March 1, 1964
Creator:
Rider, B. F.; Peterson, J. P., Jr.; Ruiz, C. P. & Smith, F. R.
Object Type:
Report
System:
The UNT Digital Library
Accurate Nuclear Fuel Burnup Analysis. Thirteenth Quarterly Progress Report, December 1964-February 1965
None
Date:
March 1, 1965
Creator:
Rider, B. F.; Ruiz, C. P.; Peterson, J. P., Jr.; Seymour, R. S.; Jaech, J. L. & Smith, F. R.
Object Type:
Report
System:
The UNT Digital Library
Adaptation of a Commercial Counter X-Ray Diffractometer for Investigations to 3000°C
The rapid advances in many technologically important areas have not only served to accentuate the increased demands for high temperature metals and ceramics but have necessitated a more through knowledge of their physical properties when exposed to high temperature service. Toward this latter end, the use of X-ray diffraction has proved an invaluable tool in providing data of regions of thermal stability, expansion coefficients, solid solubility limits, and phase transformations by direct examination at temperature. Since this Laboratory has for some time now been engaged in the study of refractory nuclear materials, it was thought desirable to employ and possibly extend this technique to temperatures ranging up to 3000°C. This communication will describe the equipment developed for this purpose, with experimental results to be described in subsequent publications.
Date:
March 12, 1963
Creator:
LaPalca, Samuel; Farber, Gerald & Adler, George
Object Type:
Report
System:
The UNT Digital Library