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Nuclear Analysis of Pm Long-Life Core 3
None
Date:
October 31, 1964
Creator:
Bagley, R. & George, C.
System:
The UNT Digital Library
Fuel Management in Large Pressurized Water Reactors
Economic and operational ground rules and their effects on fuel management are summarized, and examples showing the approach to typical fuel management problems are presented. The problems associated with in-core fuel management are also discussed, and the merits of various fuel cycling methods are evaluated. (D.C.W.)
Date:
October 31, 1964
Creator:
Dollard, W. J. & Strawbridge, L. E.
System:
The UNT Digital Library
Applications of Monte Carlo Calculations to SGR Reactors
Monte Carlo (MC) calculations were made that show that an observed reactivity increase due to fuel rod bowing in the Sodium Reactor Experiment can be accounted for by the accompanying change in the thermal flux distribution. The questionable reliability of calculations with a simplified fuel element model that indicated the same relation prompted the MC calculations. Comparison with experimental results and results calculated by other means established the reliability of the MC calculations. (D.C.W.)
Date:
October 31, 1964
Creator:
Fillmore, F L
System:
The UNT Digital Library
Simplified Analytical Model for Simulation of Boiling Water Reactors
A digital computer program FLARE was developed for calculating the core reactivity and power distributions in the Big Rock Point Reactor. The calculations are restricted to a relatively coarse mesh, but good agreement was obtained in comparisons with operating data from the Kahl reactor. (D.L.C.)
Date:
October 31, 1964
Creator:
Fischer, D. L. & Harriman, J. M.
System:
The UNT Digital Library
Operating Strategy for Maintaining an Optimum Power Distribution Throughout Life
A method of operation developed for maintaining a minimum power peaking factor throughout the operating cycle of a power reactor is described. The basic operating principle for peaking factor minimization is presented, and its use in the design phase to compare and set design parameters and in the operational phase to establish control rod patterns is outlined. The method will (hopefully) increase the power density in the Big Rock Point Reactor. (D.C.W.)
Date:
October 31, 1964
Creator:
Haling, R. K.
System:
The UNT Digital Library
Application of the Variational Method to the Calculation of the Time Dependence of the Neutron Flux in Small Pulsed Slabs, Cylinders and Spheres
The variational method is applied to the monoenergetic time dependent transport equation to obtain a simple relation for the asymptotic decay constant in small pulsed assemblies. The results indicate that flat trial functions may be a reasonable representation of the flux distributions in the thin slab limit. This approach is superior to many of the usual transport approximations. (auth)
Date:
October 31, 1964
Creator:
Judge, F. D. & Daitch, P. B.
System:
The UNT Digital Library
Fabrication and Properties of Seamless Tungsten Tubing
A process for the production of seamless tungsten tubing is described. The process consists of the extrusion of sintered powder sleeves at elevated temperatures to sizes close to the final dimension. The tubing is finished by warm drawing. A size range of 0.100-in, diameter to 1 1/2-in. diameter has been fabricated. A preliminary evaluation of properties of the extruded tubes is given. (auth)
Date:
October 31, 1964
Creator:
Loewenstein, P.; Hunt, J. G. & Jenkins, R. G.
System:
The UNT Digital Library