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BOUNDARY CONDITIONS AND CONSERVATION PROPERTIES OF FOPP, A PLASMA FOKKER- PLANCK CODE (open access)

BOUNDARY CONDITIONS AND CONSERVATION PROPERTIES OF FOPP, A PLASMA FOKKER- PLANCK CODE

The energy distribution of ions and electrons in DCX are being studied by means of the Fokker-Planck approximation to the Boltzmann equation. An IBM- 704 code, called FOPP, was constructed to solve simultaneously the coupled Fokker-Planck equations for each of the two species of particles. This report discusses the difference scheme employed and derives the boundary conditions necessary in order that this difference scheme conserve energy and particles in the absence of sources and sinks. In particular, detailed discussion is given of problems arising from the use of two grid sizes, which proved advantageous on account of the great difference in the mass of ions and electrons. (auth)
Date: February 27, 1959
Creator: Fowler, T.K.; Rankin, F.M. & Simon, A.
System: The UNT Digital Library
Fuel Cycle Costs in a Graphite Moderated U$sup 235$-Th Fueled Fused Salt Reactor (open access)

Fuel Cycle Costs in a Graphite Moderated U$sup 235$-Th Fueled Fused Salt Reactor

A fuel-cycle economic study was made for a 315-Mw(e) graphite-moderated U/sup 235/-Th-fueled fused-salt reactor. Fuel cycle costs of approximately 1.3 mills/kwh may be possible for such reactors when reprocessed for U/sup 233/ and U/ sup 235/ recover y at the end of a 9-year cycle. Continuous removal of fission products during the reactor cycle does not appear to offer any great economic advantage for the converter reactor considered. (auth)
Date: February 27, 1959
Creator: Guthrie, C. E.
System: The UNT Digital Library
SM-2 VAULT CRITICALITY (open access)

SM-2 VAULT CRITICALITY

To determine the safety of the array in the storage vault for the SM-2 experimental fuel plates, two criticality criteria were applied. A maximum of 18 fuel plates was stored in sthainless steel tubes and the tubes belted to a frame on the wall to prevent movement. No tube could go critical by itseIf. The vauit was then assumed completely flooded by water. In the first calculation, the fuel array was assumed to be distributed uniformly over the wall forming a large slab. This method indicated the array might be critical if the steel tube and cadmium lining were neglected. In the second method, a conservative calculation, wnich included the steel tube and cadmium lining was made. This method indicataed the array was subcritical. Calculations were then made of the criticalty of the SM-2 vault without the steel--cadmium tubes and wcoden blocks. The multiplication factor of the vault was also calculated. In order to determine the accuracy of these calculations, an ORNL critical experimental array was calculated applying the same analytical techniques. (M.C.G.)
Date: February 27, 1959
Creator: Fried, B.E.
System: The UNT Digital Library
SUMMARY OF RUNS D-77 THROUGH D-93. RATE OF OXIDATION OF CHROMIUM(III) IN DILUTE URANYL SULFATE SOLUTION IN THE PRESENCE OF RUTHENIUM (open access)

SUMMARY OF RUNS D-77 THROUGH D-93. RATE OF OXIDATION OF CHROMIUM(III) IN DILUTE URANYL SULFATE SOLUTION IN THE PRESENCE OF RUTHENIUM

The rate of oxidation of chromium(III) to chromium(VI), catalyzed by ruthenium, was determined at various temperatures and oxygen concentrations. The rate at 300 deg C was too rapid for measurement by aliquot sampling. In the temperature range of 225 to 275 deg C, oxidation was rapid and the rate increased with oxygen concentration. A linear dependence of initial oxidation rate on the reciprocal of chromium(VI) concentration suggested that a rate-controlling step in the reaction mechanism may be desorption of chromium(VI) from the ruthenium catalyst. The activation energy calculated for the reaction is 19 kcal/mole. (auth)
Date: February 27, 1959
Creator: Snavely, E.S.; Greeley, R.S. & Buxton, S.R.
System: The UNT Digital Library