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Modified Murnaghan equation of state applied to shock compression of silica, basalt, and dolomite
An equation of state previously used by the author is developed further and applied to geologic media. The equation is of the same form as the Murnaghan equation of state, but with the elastic constant terms replaced by the cohesive energy density (internal pressure), and the exponential term given as a sum of the Gruneisen parameter and the gaseous adiabatic exponent. Data for shock compression of silica, basalt, and dolomite are analyzed according to the equation.
Date:
December 20, 1965
Creator:
Rogers, L.A.
Object Type:
Article
System:
The UNT Digital Library
Letter to Mr. Frank Rom, National Aeronautics and Space Administration, Lewis Research Center, Cleveland, Ohio
None
Date:
May 20, 1965
Creator:
Albaugh, F. W.
Object Type:
Report
System:
The UNT Digital Library
Tritium extraction facility study - 1965
This study was prepared in support of AEC-requested reactor case studies. Two of the cases include local separation and purification of tritium from Hanford irradiated aluminum-lithium alloyed slugs after 1974, at which time, the Savannah River Plant would be shut down. Consideration is given to processing N Reactor rods or {open_quotes}K{close_quotes} Reactor I&E slugs. Quantities of tritium to be produced would be five kilograms per year in one case and seven kilograms per year in the other case. The facility would process tritium only through the purification stage. At this point the material would be shipped offsite for storage, packaging and any future weapon stockpile rework.
Date:
August 20, 1965
Creator:
Kesel, G. P. & Wodrich, D. D.
Object Type:
Report
System:
The UNT Digital Library
Development test IP-778: KE downcomer increased flow test
To determine the present flow properties of the KE downcomer and the effect of small flow increases upon the downcomer pressure characteristics.
Date:
May 20, 1965
Creator:
Jones, S. S.
Object Type:
Report
System:
The UNT Digital Library
Reactor effluent analytical data: October--December 1964
This report continues the tabulation of reactor effluent data for record purposes. During this report period, al reactor coolant had sodium dichromate added to a concentration of 1.0 ppm. coolant for both of the K Reactors was treated with liquid alum at a rate of about 12 ppm. Bauxite was used at all other reactors to provide a nominal alum concentration of 18 ppm during treatment. The coolant pH at DR, F, KE, and KW was reduced from 7.0 to 6.6 on October 23, October 29, December 5, and December 6, 1964, respectively. By the end of the report period, pH 6.6 coolant was in use at all reactors.
Date:
January 20, 1965
Creator:
Koop, W. N.
Object Type:
Report
System:
The UNT Digital Library
Production Test IP-745: Half-plant validity test, Final report
Half-plant production tests have been used for many years to evaluate changes in water treatment processes. Since some conjecture existed regarding the validity of this test concept, it was decided to employ a tracer element. Bromine was chosen as the tracer element due to its absence in raw water, the short half life of its radionuclides, and its compatibility as a potable water treatment chemical. The parent production test was run for four days, but the scatter in the data indicated equilibrium had not been reached and conclusions could not be made. The test supplement was run for a period of 12 days. This report provides the test data which shows that an average cross flow of 7.6% is experienced, as measured in the reactor rear riser, when a reasonably balanced pumping system is maintained. Operating experiences at D and F Reactors during the early part of 1965 further confirm these facts. Excessive film build-up occurred in both instances on plant halves. A distinct demarkation line was experienced between vertical rows 73 and 74, as measured by front face Panellit pressure increases.
Date:
May 20, 1965
Creator:
Frymier, J. W.
Object Type:
Report
System:
The UNT Digital Library
Evaluation testing of the CEC type 4-125 and 4-126 velocity transducers
None
Date:
August 20, 1965
Creator:
Pappas, T.A.
Object Type:
Report
System:
The UNT Digital Library
Activation plan for the W-1 loop
This report defines the work program and schedule required to Activate the plan for the W-1 loop
Date:
December 20, 1965
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Final SNAPSHOT safeguards report. Addendum I
None
Date:
March 20, 1965
Creator:
Hart, R.S. (ed.)
Object Type:
Report
System:
The UNT Digital Library
PRIMARY PIPING FLEXIBILITY ANALYSIS FOR LIQUID-METAL-COOLED FAST BREEDER REACTORS
None
Date:
August 20, 1965
Creator:
McKeon, J. T.
Object Type:
Report
System:
The UNT Digital Library
HIGH-TEMPERATURE MATERIALS PROGRAM. Progress Report No. 54, Part A
None
Date:
December 20, 1965
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Mound Laboratory Progress Report For August 1965
Reports current technical interest of Mount Laboratory in research and development programs.
Date:
August 20, 1965
Creator:
Eichelberger, J.F.; Grove, G.R. & Jones, L.V.
Object Type:
Report
System:
The UNT Digital Library
Finite Difference Methods for Nonlinear Radiation Transport
None
Date:
August 20, 1965
Creator:
Campbell, P. M.
Object Type:
Report
System:
The UNT Digital Library
REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, SEPTEMBER 1965
None
Date:
October 20, 1965
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
LARGE VOLUME IMPACTOR COLLECTOR. Report No. 2893
None
Date:
December 20, 1965
Creator:
Zeller, H.
Object Type:
Report
System:
The UNT Digital Library
Interim report on the SNAP critical assembly 4A (SCA-4A) experimental results
None
Date:
March 20, 1965
Creator:
Clifford, D.W.
Object Type:
Report
System:
The UNT Digital Library
Comparison of WANL Corrosion Data With ICAP: HHT-6.2-1, Short Slit
In order to test the relationships used for reactor corrosion predictions an attempt was made to compare these calculations with the data obtained on a laboratory corrosion experiment.
Date:
August 20, 1965
Creator:
Kanter, I.E.
Object Type:
Report
System:
The UNT Digital Library
Seven-Point Difference Equations With Arbitrary Mesh Spacing for Neutron Diffusion in 60 Deg Geometry by the Integration Technique
None
Date:
January 20, 1965
Creator:
Gast, R. C.
Object Type:
Report
System:
The UNT Digital Library
Strain Gage Applications Using the Rodide Process
None
Date:
August 20, 1965
Creator:
Anderson, L. J.
Object Type:
Report
System:
The UNT Digital Library
RADIONUCLIDE FRACTIONATION IN AIR-BURST DEBRIS
None
Date:
September 20, 1965
Creator:
Freiling, E.C. & Kay, M.A.
Object Type:
Report
System:
The UNT Digital Library
MEASURING THE CROSS-SECTIONS FOR THE REACTIONS $nu$e + p$Yields$n + $beta$$sup +$ AND $nu$e + D$Yields$2n + $beta$$sup +$
None
Date:
January 20, 1965
Creator:
Jenkins, T L & Reines, F
Object Type:
Report
System:
The UNT Digital Library
Buckling Tests of Scaled Graphite Barrel Inner Reflectors
This report addresses the buckling tests of scaled graphite barrel inner reflectors.
Date:
July 20, 1965
Creator:
Krebs, A.N.
Object Type:
Report
System:
The UNT Digital Library
REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, MARCH 1965
None
Date:
April 20, 1965
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Analog Computer Analysis of Magnetic Tape Seismograms.
None
Date:
January 20, 1965
Creator:
Lynch, Robert
Object Type:
Report
System:
The UNT Digital Library