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Serial/Series Title
Chemical Processing Department Monthly Report
60
Irradiation Processing Department Monthly Report
25
Notes of Monthly Component Test Program Review Meeting Held with SNPO at WANL
25
Hanford Laboratories Operation Monthly Activities Report
24
ANL Reactor Development Program Progress Report
14
Project Chariot
13
Project Sedan
11
Pacific Northwest Laboratory Monthly Activities Report
8
Project Pre-Schooner 2
8
ACRH Semiannual Report on Medical Research
7
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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
T = 0 and T = 1 Pairing in Light Nuclei.
None
Date:
January 1, 1969
Creator:
Goodman, A. L.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
1.5% boron, stainless steel
A test report on the brittleness of borated steel to be used in the KIWI B-5 shield capsules.
Date:
September 19, 1962
Creator:
Schreiber, J.J.
Object Type:
Report
System:
The UNT Digital Library
A 1.5 Mwe Thermionic Reactor Space Power System
None
Date:
October 31, 1966
Creator:
Smith, C. K. & Parkinson, R. Y.
Object Type:
Report
System:
The UNT Digital Library
E-1 Common Analog Model (U)
This report is the descriptive description of the E-1 common analog model
Date:
July 1, 1969
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
04 nuclear safety: pressure piping crack monitoring detection of metal overstress by acoustic emission. Progress report, July-September 1966
The three main areas of effort have been: (1) definition of the general acoustic response pattern related to the gross aspects of forming and extending a crack in various materials, (2) development of a monitor system prototype concept exclusive of transducers and (3) development of a suitable, high temperature transducer. Tests using double cantilever beam (DCB) specimens of various materials to establish conditions of crack formation and growth have indicated that material ductility is a major controlling factor in the acoustic response pattern. It appears to effect both acoustic emission intensity and the point in the crack formation-growth sequence at which the main emission occurs. A concept has been developed for the prototype of a full scale monitor system. Hardware development is being limited to the analyzer portion of the system at this time because it is the part most significant to demonstrating feasibility of the intended application. Signal level and signal rate are both being investigated as possible parameters for evaluating acoustic emission data. Of the various transducers for potential high temperature application, the capacitive or electrostatic transducer now looks most promising. A significant improvement in sensitivity has been achieved and a trial model used during recent tests produced …
Date:
October 28, 1966
Creator:
Hutton, P H
Object Type:
Report
System:
The UNT Digital Library
5 and 5 hot cell configuration for E-MAD facility. Phase 2
None
Date:
January 17, 1963
Creator:
Svasek, A. J.
Object Type:
Report
System:
The UNT Digital Library
A 5 mechanical test of core support block. Preliminary report
This report contains seven different configurations of support blocks.
Date:
September 30, 1963
Creator:
Lee, D. Y.
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
10-30 Bev/c ELASTIC SCATTERING OF $pi$$sup +-$+ p, p + p, /anti p/ + p AND K$sup +-$ + p OVER THE /t/ RANGE 0.0005 TO 1 (Bev/c)$sup 2$
None
Date:
July 28, 1964
Creator:
Foley, K. J.; Gilmore, R. S.; Jones, R. S.; Lindenbaum, S. J.; Love, W. A.; Ozaki, S. et al.
Object Type:
Report
System:
The UNT Digital Library
A-11 seven cluster model: FFL-10 solid core tests
This report summarizes the results of the seventh and last of a series of tests completed in the A-11 test program during the Contract Year 1964
Date:
December 18, 1964
Creator:
Cherish, P. & Leff, G.J.
Object Type:
Report
System:
The UNT Digital Library
A-11 seven cluster model: Phase V, flow induced vibration tests
This report summarizes the results of the fifth of a series of tests completed in the A-11 test program.
Date:
September 29, 1964
Creator:
Cherish, P. & Leff, G.J.
Object Type:
Report
System:
The UNT Digital Library
12-INCH SODIUM FLOW CONTROLLER. Technical Manual 20357
A manual is presented for the Sodium Flow Controller used in controlling flow to regulate heat transfer in a liquid metal nuclear power plant. A description of the controller, general installation and operational pointers, installation instructions, instructions for dismantling of the Sodium Flow Controller, instructions for assembly of Sodium Flow Controller, list of special tools and fixtures, and repair parts list are given. (M.C.G.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
12" SODIUM FLOW CONTROLLER. PERMANENT MAGNET COUPLING. MAGNETIC CALCULATION MANUFACTURE AND TEST RESULTS
In order to retain the hermetic feature of the sodium flow controller, magnetic flux linkage of a permanent magnet coupling is used to transmit the torque produced by the operator through the pressure wall. Magnetic calculations, manufacture, and testing of this magnet coupling are described. (M.C.G.)
Date:
August 18, 1961
Creator:
Flator, H.E.
Object Type:
Report
System:
The UNT Digital Library
13-Watt Curium Fueled Thermoelectric Generator for a Six-Month Space Mission. Final Report
None
Date:
July 1, 1960
Creator:
Bloom, J. L.
Object Type:
Report
System:
The UNT Digital Library
13-Watt Curium-Fueled Thermoelectric Generator for Hard Lunar Impact Mission. Final Report-Subtask 5.8
Results of a conceptual design study for a curium powered thermoelectric generator of minimum size and weight which is capable of sustaining hard impact is presented. The generator produces a minimum of 13 watts of d-c power at 3 volts, and weighs 6.2 pounds excluding shielding. (J.R.D.)
Date:
August 1, 1960
Creator:
Bloom, J. L.
Object Type:
Report
System:
The UNT Digital Library
14-Inch Swing Check Valve Test
The check valve for the Hallam Power Reactor uses a knife-edge bearing for the flapper in place of the usual journal-type bearing. Mechanical cycling in sodium at 600 deg F was used to check operation of this bearing. A total of 309 mechanical cycles was completed with no apparent malfunctioning of the valve. Measured leskage rates were 0.46 gpm at 0.93 psig, 0.73 gpm at 3.4 psig. and 0.32 gpm at 5.9 psig. (M.C.G.)
Date:
February 10, 1960
Creator:
Cygan, R.
Object Type:
Report
System:
The UNT Digital Library
A 23-Group Neutron Thermalization Cross Section Library
A set of 23-group neutron cross sections for use in the calculation of neutron thermalization and thermal neutron spectral effects in SNAP reactors is compiled. The sources and methods used to obtain the cross sections are described. (auth)
Date:
July 15, 1963
Creator:
Doctor, R. D. & Boling, M. A.
Object Type:
Report
System:
The UNT Digital Library
The 25-Inch Liquid Hydrogen Bubble Chamber
None
Date:
May 25, 1964
Creator:
Barrera, F.; Byrns, R. A.; Eckman, G. J.; Hernandez, H. P.; Norgren, D. U.; Shand, A. J. et al.
Object Type:
Report
System:
The UNT Digital Library
40-Mw(e) Prototype High-Temperature Gas-Cooled Reactor Postconstruction Research and Development Program. Quarterly Progress Report for the Period Ending April 30, 1965
None
Date:
May 31, 1965
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
40-Mw(e) Prototype High-Temperature Gas-Cooled Reactor Postconstruction Research and Development Program. Summary Progress Report for the Period Ending, October 1964
None
Date:
December 15, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
40-MW(e) Prototype High-Temperature Gas-Cooled Reactor Research and Development Program. Quarterly Progress Report for the Period Ending June 30, 1962
Research and development progress specifically directed toward the construction of a 40-Mw(e) prototype power plant employing a high-temperature, gas-cooled, graphitemoderated reactor known as the HTGR is reported. Irradiation of element III-B in the in-pile loop continued satisfactorily. The element has generated a total of l36.3 Mw-hr of fission heat. The gross activity in the purge stream increased slightly to about 350 mu C/cm/sup 3/. By taking larger gas samples than were previously taken, a value of 0.02 VC/cm/sup 3/ was obtained for the gross activity of the primary loop. Element III-A, which was removed from the loop after generating 133 Mw-hr of fission heat, was disassembled and examined. No fuel-compact damage of any type was visible. Determination of the distribution of fission products in the element is under way, Fissionproduct- release data for in-pile-loop element III-A were calculated. During the 133 Mw- hr of operation, the release fraction increased by approximately one order of magnitude. Also calculated were the xenon and krypton release data for the first 100 Mw-hr of III-B operation. The release rate for the longer-lived isotopes increased bv about a factor of 10 and that of the shorter-lived isotopes by about a factor of 100. A test …
Date:
October 31, 1963
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
40-Mw(E) Prototype High-Temperature Gas-Cooled Reactor. Research and Development Program. Quarterly Progress Report for the Period Ending March 31, 1963
None
Date:
October 31, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Summary Report for the Period January 1, 1959-December 31, 1959 and Quarterly Progress Report for the Period October 1, 1959-December 31, 1959
The HTGR prototype plant (Peach Bottom Power Reactor) is being designed to produce steam at l450 psi and 1000 deg F and to have a net capacity of 40 Mw(e). The fuel temperatures and gas pressures will be approximately the same as those required for larger plants. The reactor data and operating conditions for the graphite-clad core are given. The reactor and primary coolant systems are described. The prospects for development of the graphite-clad fuel element in time for use in the first loading of the reactor were improved by important advances in methods of fabrication and testing of both fuel compacts and graphite sleeves. The hot-pressing process for making fuel compacts was used successfully to make full-size compacts with a uniform distribution of ThC/sub 2/- UC/sub 2/ particles. Three irradiation capsules were fabricated and inserted in a test reactor to determine fuel compact and sleeve performance under HTGR conditions of irradiation and temperature. Two of these ran satisfactorily for the scheduled time of operation. A scope design study of the in-pile loop that will be used to evaluate the full-diameter graphite-clad element was completed. Experiments to determine the extent of fuel migration within the element were undertaken. Preliminary results …
Date:
September 1, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library