Decade
Year
Day
16 Matching Results
Results open in a new window/tab.
Results:
1 - 16 of
16
Fiscal 1965 revision of cesium-137 index for nuclear materials content of coating waste
None
Date:
August 19, 1964
Creator:
Zimmer, W. H.
System:
The UNT Digital Library
Thermal shield cooling tube surveillance: B, C, D, and K Reactors
The top thermal shields of the Hanford reactors were formed by placing single layers of large cast iron blocks on the top of the graphite stacks. Accumulative distortion of the graphite stack is causing several inches of variation in the elevation of the originally level top thermal shields. The integrity of the top thermal shield cooling tubes is of concern because of the high axial and bending stresses they are subjected to from the shield variations in addition to the normal service conditions common also to the side and bottom thermal shields. Concern for possible deteriorating condition of the top cooling tubes has increased with the discovery of a leaking cooling tube at the C Reactor. This report provides information of the present condition of the cooling tubes and discusses continued surveillance of their condition which is required for evaluation of their continued serviceability.
Date:
November 19, 1964
Creator:
Bonham, C. E.
System:
The UNT Digital Library
Fission product formation in fuel elements
None
Date:
February 19, 1964
Creator:
Shields, R. J.
System:
The UNT Digital Library
Plutonium, neptunium and americium waste tank inventories
None
Date:
October 19, 1964
Creator:
Warren, J. H.
System:
The UNT Digital Library
Design of the Snap-15A Generator
This report summarizes the considerations and analysis leading to the design of the SNAP-15A generator, a Pu-238 fueled, metal thermocouple generator providing about 1 milliwatt of output power at greater than 4, 5 volts of years with very reliability even under extreme environmental conditions.
Date:
June 19, 1964
Creator:
Campana, R.J.
System:
The UNT Digital Library
PREPARATION AND CELL PARAMETERS OF LuB$sub 2$C$sub 2$
None
Date:
November 19, 1964
Creator:
Nordine, P. C.; Smith, G. S. & Johnson, Q.
System:
The UNT Digital Library
Properties of AISI type 347 stainless steel above 1500$sup 0$F
None
Date:
August 19, 1964
Creator:
unknown
System:
The UNT Digital Library
Specific Zirconium Alloy Design Program. Summary Report
None
Date:
May 19, 1964
Creator:
Klepfer, H. H.
System:
The UNT Digital Library
Fire-Retardant Coatings
None
Date:
May 19, 1964
Creator:
Gaskill, J. R.
System:
The UNT Digital Library
Control Drum Bearings, Experiment No. 40/W004, Irradiated at Plum Brook Reactor Facility, PBRF Cycle 6 (PB No. 2W). Preliminary Data Report
Preliminary results of the irradiation of control drum bearings in a static test, conducted at the Plum Brook Reactor Facility in Sandusky, Ohio, on October 14-15, 1963, are described in this report.
Date:
February 19, 1964
Creator:
Stephens, A. G.
System:
The UNT Digital Library
LOOP CURRENTS IN A SYSTEM OF INDUCTIVELY COUPLED, SEQUENTIALLY ENERGIZED AND CROW-BARRED COILS
None
Date:
May 19, 1964
Creator:
Ellis, R.E.
System:
The UNT Digital Library
Bendix TPCV Actuator Presentation
This report addresses the Bendix TPCV actuator presentation.
Date:
March 19, 1964
Creator:
unknown
System:
The UNT Digital Library
Mark III TPA stability analysis
None
Date:
March 19, 1964
Creator:
unknown
System:
The UNT Digital Library
Heavy-Water-Moderated Power Reactors Cooled by Liquid D$sub 2$O or H$sub 2$O
None
Date:
March 19, 1964
Creator:
Boswell, J. M.; Holmes, W. G.; Hood, R. R.; Ross, C. P.; St. John, D. S. & Wade, J. W.
System:
The UNT Digital Library
DATA SIMULATION WITH AN ON-LINE COMPUTER AS A DIAGNOSTIC AND ANALYTICAL TOOL
A hybrid approach was adopted in the use of an on-line computer in setting up and analyzing nuclear physics experiments. In addition to the usually cited advantage of online flexibility and the ability to do off-line calculations, the general purpose computer can simulate data by preserting the results of off-line calculations to the experimenter in a format identical to that used for data display. As compared with off-line calculations at a computer center with subsequent hand or machine plotting, the use of the build-in display hardware provides a more convenient comparison of theory with experiment, as well as greater ease and speed. The advantages of on-line data transformation are preserved without accompanying limitations on the rate of data taking. The data from the experiment consisted of energy correlations in two-particle coincidence experiments. The loci of points in energy-energy space fulfilling energy and momentum conservation were calculated, displayed, and photographed before each experimental run. Interpretation of the experimertal data was assisted by modulation of the loci (of the number of counts per channel) according to the predictions of various models. (auth)
Date:
February 19, 1964
Creator:
Mollenauer, J.F.
System:
The UNT Digital Library
1000-Mwe SGR. 90% ThO₂, 10% UO₂ Alternate Fuel Core Thermal and Hydraulic Analysis
The thermal and hydraulic core parameters were determined using the SORTD I code for 90% ThO/sub 2/, 10% UO/sub 2/ fuel both for (1) a core containing 592 fuel elements corresponding to the UC reference core with a maximum UC temperature of 2000 deg F and (2) a core containing 784 fuel elements corresponding to a UC core with a maximum UC temperature of 1750 deg F. Eighteen rod elements with 2.5 in./sup 2/ and 3.5 in./sup 2/ fuel areas, and 30 rod elements with 4.5 in./sup 2/ and 5.5 in./sup 2/ fuel areas are analyzed for 8 cases. (auth)
Date:
February 19, 1964
Creator:
Imig, J. K.
System:
The UNT Digital Library