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Superconductivity in solid solutions of transition metal carbides. [NbC-TaC]
None
Date:
June 10, 1964
Creator:
Wells, M.
System:
The UNT Digital Library
Hydrogeology at hydrologic test well HT-3 and correlation of aquifers, Tatum Dome, Lamar County, Mississippi
None
Date:
August 10, 1964
Creator:
Lockwood, W.N.
System:
The UNT Digital Library
Analysis of the Third H-Reactor Core Load
None
Date:
February 10, 1964
Creator:
Ringle, R. P.
System:
The UNT Digital Library
Neptunium-237 production forecasts, IPD 1964--73
Neptunium-237 production has been-calculated according to the equations documented in Reference 1 for use in 1964-AEC study. cases. The assumptions made in the forecasts are as follows: Only the 947 stream is recycled. The blend enrichment for the recycle maternal is 1.2 per cent for F-Y 64 and 65. For FY 66 -73, a blend enrichment of 1.4 per cent is assumed which is better value according to the optimization model of C. W. Showalter. The 947 stream recycle time is two years. In cases A and B where the 947 stream volume is materially increased, virgin 947 material is introduced to make up the material balance. The U-236 content of the blend material- is 66 ppm{sup 2}. The U-236 input level in the 947 stream for the input of FY 64 is 200 ppm{sup 1}. Separations recovery is 85 per cent for FY 64--65 and 90 per cent thereafter. The material throughput data are given in Table I. These values are consistent with those being assumed for the AEC study cases. The Kgs of Np-237 by fiscal year are given in Table II. It must be remembered that these forecasts are based on a particular set of idealized assumptions, …
Date:
July 10, 1964
Creator:
Nilson, R.
System:
The UNT Digital Library
Design test request No. 1263 K Reactor graphite key and VSR channel sleeve test
The objectives of this test were: (1) Determine the coefficient of friction between two adjacent layers of K Reactor graphite at room temperature. (2) Determine the average load required to cause failure of an unirradiated K Reactor side reflector bar, when subjected to tensile loading applied through the reflector keys. (3) Determine the average load at failure and the average deflection at failure of a single VSR channel key when loaded in keyways with clearances equal to those used in original stack construction. (4) Determine the average load and deflection required to break the four K Reactor VSR keys when loaded simultaneously in both `3-layer` and `7-layer` mockups. Also determine the mode of key failure; i.e., shear, flexure or combined compression and bending. Following these key rupture tests, determine the strength and deflection characteristics of the proposed K Reactor VSR channel sleeve when loaded in a manner identical to that used to fracture the keys. (5) Determine the average load and deflection at failure of both the proposed K Reactor VSR channel sleeves and the proposed C Reactor sleeves when subjected to crushing loads. (6) Determine the extent of damage to the proposed K Reactor VSR channel sleeve when subjected …
Date:
December 10, 1964
Creator:
Kempf, F. J.
System:
The UNT Digital Library
Physics aspects of removal of overbore test facility
Investigation of several alternative methods of modifying the C- Reactor overbore test facility in order to terminate the production tests has been completed. The results are presented in this report.
Date:
August 10, 1964
Creator:
Bailey, G. F.
System:
The UNT Digital Library
Results of air entry control test No. 1 DR Reactor
This report discusses testing conducted to establish an interim normal limit for nitrogen concentration in the reactor gas; obtained information to be used in defining assuredly positive gas system pressure; and obtain other useful information on the reactor gas system, such as total apparent system volume, accuracy of the gas activity meter at low nitrogen cencentrations, etc.
Date:
February 10, 1964
Creator:
George, D. K.
System:
The UNT Digital Library
Interim normal limits DR reactor
As specified in PITA IP-26-I, a test has been conducted at DR reactor to find the amount of nonpressure sensitive air entering the reactor, and gain other information on the reactor gas system. The purpose of this document is to place in effect interim normal gas purity limits and define assuredly positive gas system pressure based on the results of this test.
Date:
February 10, 1964
Creator:
George, D. K.
System:
The UNT Digital Library
Irradiation Test of the GAIL III-B Fuel Element in the General Atomic Inpile Loop
None
Date:
July 10, 1964
Creator:
Turner, R. F.; Baumgartel, R. G.; Leon, H. I.; Winkler, E. O. & Zumwalt, L. R.
System:
The UNT Digital Library
STRAIN GAGE TEST AT THE THREADED CLOSURE ON A THIRTY-INCH PRESSURE VESSEL
None
Date:
August 10, 1964
Creator:
Long, P. J. & Ross, W. D.
System:
The UNT Digital Library
Portable Battery-Operated High-Volume Air Sampler
None
Date:
June 10, 1964
Creator:
Lindeken, C. L. & Taylor, R. D.
System:
The UNT Digital Library
DEVELOPMENT OF FLUIDIZED BED CHLORINATION FOR CONVERTING PuO$sub 2$ TO PuCL$sub 3$
None
Date:
July 10, 1964
Creator:
Brandt, H. L.
System:
The UNT Digital Library
Barrier-Planning With Nuclear Cratering Explosives
None
Date:
July 10, 1964
Creator:
Circeo, L. J., Jr.
System:
The UNT Digital Library
FABRICATION OF TEFLON BY HYDROSTATIC PRESSING
None
Date:
August 10, 1964
Creator:
Church, J.S.; Donahoe, J.K. & Sheinberg, H.
System:
The UNT Digital Library
A Note on Surface Waves on a Sloping Beach
None
Date:
November 10, 1964
Creator:
Yee, K. S.
System:
The UNT Digital Library
Nuclear Cratering Experience at the Pacific Proving Grounds
None
Date:
November 10, 1964
Creator:
Circeo, L. J., Jr. & Nordyke, M. D.
System:
The UNT Digital Library
Evaluation of plasma-sprayed pyrolytic graphite components
None
Date:
January 10, 1964
Creator:
Goodspeed, R.C.
System:
The UNT Digital Library
Preliminary data report: linear displacement transducers, experiment No. 23/W202, irradiated at Plum Brook Reactor Facility, PBRF cycle 6 (PB No. 3W)
None
Date:
March 10, 1964
Creator:
Stephens, A. G.
System:
The UNT Digital Library
N-Reactor Department monthly report, October 1964
This document details activities of the N-Reactor Department during the month of October 1964.
Date:
November 10, 1964
Creator:
unknown
System:
The UNT Digital Library
N-Reactor Department monthly report, July 1964
This report details activities of the N-Reactor Department during the month of July 1964.
Date:
August 10, 1964
Creator:
Dickeman, R. L.
System:
The UNT Digital Library
N-Reactor Department monthly report, November 1964
This report details activities of the N-Reactor Department during the month of November 1964.
Date:
December 10, 1964
Creator:
Dickeman, R. L.
System:
The UNT Digital Library
Shutdown Reactivity by the Modified Rod Drop Method
A more accurate rod-drop method for measuring the shutdown reactivity available from control rods is outlined. Corrections due to flux shape changes can be applied to the measurements, and the use of pretimed scram equipment provides excellent reproducibility. Finite rod-drop times are also taken into account. Results for ARMF-H and ETRC are included. (auth)
Date:
March 10, 1964
Creator:
Moore, K. V.
System:
The UNT Digital Library
Design and Economic Evaluation of Mobile Blankets for Fast Reactors
None
Date:
March 10, 1964
Creator:
Klickman, A. E.; Amorosi, A.; Ball, G. L.; Edwards, J. J.; Jens, W. H.; Segal, B. M. et al.
System:
The UNT Digital Library
INVESTIGATION OF THERMAL-STRESS-FATIGUE BEHAVIOR OF STAINLESS STEELS. SUMMARY OF TEST RESULTS ON TYPES 304 AND 304-L STAINLESS STEELS
None
Date:
April 10, 1964
Creator:
Horton, K. E.
System:
The UNT Digital Library