Advanced Designs and Special Applications for Fast Breeders (open access)

Advanced Designs and Special Applications for Fast Breeders

The purpose of this paper is to describe a few of the suggested advanced concepts for fast breeder reactors and to compare these with the standard approach as to their potential advantage. I have attempted to estimate the economic effect of full technical success with each of the proposed concepts. The proposed concepts include: (1) single sodium system, (2) steam-cooled core concept, (3) direct cycle reactor using potassium as reactor coolant and working fluid, (4) molten plutonium-fuel alloy circulated and cooled by a jet of sodium, (5) settled-bed core, (6) molten salt concept, and (7) paste-fuel system.
Date: November 11, 1963
Creator: Hammond, R. Philip
System: The UNT Digital Library
Statistical Techniques Used in the Specific Zirconium Alloy Design Program (open access)

Statistical Techniques Used in the Specific Zirconium Alloy Design Program

Technical report describing the statistically designed empirical approach being used to choose a candidate Zr alloy optimum with respect to corrosion and hydriding rates in steam and having acceptable mechanical properties. The statistical techniques used and the reasons for their use are discussed in detail, with emphasis on the estimation of corrosion rates. Estimation of response surfaces is also considered.
Date: November 11, 1963
Creator: Jaech, John L.
System: The UNT Digital Library
Reactor Safety and Fuel Cycle Economics Considerations for Fast Reactors (open access)

Reactor Safety and Fuel Cycle Economics Considerations for Fast Reactors

Abstract: A core design study of a 10 Mwe fast ceramic reactor is presented. Local reactivity coefficients, safety criteria, accident analyses, and economics are considered. An attempt is made to find a new balance of characteristics by purely geometric devices, i.e., by exploring the sodium : fuel ratio and varying the height : diameter ratio of the core. The use of BeO in the core was also investigated.
Date: November 11, 1963
Creator: Cohen, K. P.; Greebler, P.; McNelly, M. J.; Murphy, P. M.; Sherer, D. B. & Zebroski, E. L.
System: The UNT Digital Library
Water Spectra and Energy Exchange Kernels (open access)

Water Spectra and Energy Exchange Kernels

Many measurement of neutron spectra have been made in water assemblies. In these system a large part of the spectrum is given by an essentially Maxwellian distribution at the moderator temperature which is insensitive to the scattering model. Hence, the test of the energy exchange scattering kernel is in the difference of the spectrum and the fundamental or Maxwellian component. The figure shows the spectrum for the Nelkin model. Once the fundamental has been subtracted neither theoretical model seems to fit the data extremely well. Below kT the Nelkin model is a closer fit than the gas model but it underestimates the deviation from the Maxwellian whereas in the joining region it overestimates the distortion.
Date: July 11, 1963
Creator: Daitch, Paul B. (Paul Bernard), 1925- & Ohanian, M. J.
System: The UNT Digital Library
Neutron Physics Division Annual Progress Report, September 1, 1962 (open access)

Neutron Physics Division Annual Progress Report, September 1, 1962

Report containing a series of reports from members of the Oak Ridge National Laboratory's Neutron Physics30 Division.
Date: January 11, 1963
Creator: Oak Ridge National Laboratory. Neutron Physics Division.
System: The UNT Digital Library