Analysis of E-N loadings (open access)

Analysis of E-N loadings

Three E-N loaded tubes were dissolved, sampled and analyzed, starting November 9, 1960. The results of these analyses and an explanation of the methods used are the subject of this report. Each tube loading received an identification code in each facility in which it was processed. All of these codes are listed for future reference. Each batch of slugs was dissolved in a preflushed dissolver. When complete solution was indicated by a leveling off of the specific gravity, two 1 ml samples were taken and analyzed for uranium, specific gravity, and excess nitric acid. The dissolver charge was digested an additional four hours. At the end of the digestion period, two 1 ml samples and one 20 ml pig sample were taken. The three samples were analyzed for U, SpG, and HNO{sub 3}. Agreement between these samples and the previous samples was taken as confirmation of complete dissolution and representative sampling. If agreement was not obtained, sampling was continued. After verification of the pig sample, six 1 ml aliquots were taken for analysis by the Analytical Control group. The remainder was aliquoted to provide material for mass analysis and for analysis by the Process Chemistry group.
Date: December 28, 1960
Creator: Zimmer, W. H.
System: The UNT Digital Library
Optimization Studies on Paste-Fueled Fast Reactors (open access)

Optimization Studies on Paste-Fueled Fast Reactors

The reference design is an unmoderated, sodium-cooled reactor using a paste fuel of uranium monocarbide in sodium. The core is a cylinder 5 ft in diameter and 5 ft in height. An 18-in. thick breeding blanket surrounds the core, and an 18-in. thick graphite reflector surrounds the blanket. Various changes were made in the reference core to uncover any possible modifications for cost reductions and to evaluate the consequences of certain design modifications which might occur. Cases were studied for variations in: fuel volume fraction in the core from 0.2 to 0.6; fertile material volume fraction in the blanket from 0.2 to 0.6; blanket thickness 3 in. to 24 in.; fuel materials of UC, U metal, UC/ sub 2/, PuC-- UC, Pu-- U metal, and PuO/sub 2/-- UC/sub 2/; and liquid carrier in the paste of Na, Sn, or Pb. (auth)
Date: December 28, 1960
Creator: Zetterbaum, J. M. & Kerlin, T. W.
System: The UNT Digital Library
Tory II-A Aerothermodynamics. Part II (open access)

Tory II-A Aerothermodynamics. Part II

This technical report describes the digital computer codes used for the aerothermodynamic calculations that were involved in evaluating the Tory II-A reactor.
Date: December 28, 1960
Creator: Uthe, P. M.
System: The UNT Digital Library
The Boundary Layer Between a Plasma and a Magnetic Field - I (open access)

The Boundary Layer Between a Plasma and a Magnetic Field - I

"The problem of a steady boundary layer or sheath between a plasma and a magnetic field is considered. A self-consistent transition layer is found which joins a uniform magnetic field at plus infinity with a collisionless field-free plasma region with arbitrary velocity distribution at minus infinity, i.e., a magnetic field profile is found such that the exact particle orbits in this field produce a current which gives rise to this field. An interesting feature of the solution is that, with any nonsingular velocity distribution at minus infinity, the magnetic field the plasma extends to infinity, exponentially attenuated, into the magnetic field region. The scale of length is the Larmor radius. Electric fields arising from charge separation in the case of particles of different mass are ignored."
Date: December 28, 1960
Creator: Grad, Harold, 1923-
System: The UNT Digital Library