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Tensile and stress rupture tests of S8DR Hastelloy-N heats: ORNL verification tests

Description: In connection with the ORR Hastelloy-N irradiation experiments, a limited number of tensile tests and uniaxial and biaxial stress-rupture tests on S8DR Hastelloy-N heats were conducted at AI to determine the effect of some of the ORNL test conditions. The tests performed at AI were in parallel to the ORNL control tests. The results showed that the effect of the test condition variations between the two tests were generally insignificant. The effect of the test conditions is discussed.
Date: October 5, 1967
Creator: Lee, S. K.
Partner: UNT Libraries Government Documents Department
open access

SOME THOUGHTS ON STABILITY IN NONLINEAR PERIODIC FOCUSING SYSTEMS

Description: A brief discussion is given of the long-term stability of particle motions through periodic focusing structures containing lumped nonlinear elements. A method is presented whereby one can specify the nonlinear elements in such a way as to generate a variety of structures in which the motion has long-term stability.
Date: September 5, 1967
Creator: McMillan, Edwin M.
Partner: UNT Libraries Government Documents Department
open access

Some Thoughts on Stability in Nonlinear Periodic Focusing Systems.

Description: A brief discussion is given of the long-term stability of particle motions through periodic focusing structures containing lumped nonlinear elements. A method is presented whereby one can specify the nonlinear elements in such a way as to generate a variety of structures in which the motion has long-term stability.
Date: September 5, 1967
Creator: McMillan, E. M.
Partner: UNT Libraries Government Documents Department
open access

Douglas United Nuclear, Inc. Report of the working committee to the Fuel Element Development Committee for activities associated with the small and K Hanford Reactors

Description: Currently the B, C, KE and KW reactors are in operation. The B and C reactors are operating to produce 12% Pu-240 in both the E metal (0.95) and natural loadings. Some columns will be taken to 15% Pu 240 on a test basis. Production of 12% Pu-240 will result in exposures of 1400 MWD/ton on natural metal and 2,000 MWD/Ton on E metal. Currently exposures are such that 10 1/2% Pu-240 has been achieved. Some control problems and temperature cycling have been encountered with this mode of operation. … more
Date: September 5, 1967
Creator: Stringer, J. T.
Partner: UNT Libraries Government Documents Department
open access

Volume increase analysis of production test 040

Description: This statistical analysis examines volume increase data from PTA-040. The purpose of this analysis is to compare four 1.25 enriched uranium core alloys (Standard, British, High Silicon, and Modified British), two heat treatments (Induction and Salt Bath), and the alloy-treatment interaction. The four core alloys were each processed using the two treatments and then canned as 5.540-in. AlSi fuel elements. Test pieces were charged in 16 tubes with 40 pieces per tube. The eight fuel types (4 alloy… more
Date: September 5, 1967
Creator: Stein, R.C.
Partner: UNT Libraries Government Documents Department
open access

Half plant activated alumina test: Final report

Description: A half reactor test was initiated at B Reactor on February 1, 1967, to determine whether the concentration of P{sup 32} and As{sup 76} in the reactor effluent water would be reduced by the addition of activated alumina in the water treatment process. This test was prompted by the reported effectiveness of activated alumina in sorption of phosphates when water flow is through a packed bed of this material. Although direct feed of material would not be expected to be as effective, testing of this… more
Date: May 5, 1967
Creator: Pitman, R.W. & Wells, G.W.
Partner: UNT Libraries Government Documents Department
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