Abstract: An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres.

"An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres. The qualitative features of the concept are sorted out and correlated by successively treating single, double, triple, and multiple layered arrays of closest packed spheres" (p. ix).

Thermal expansion characteristics were determined for fuel-moderator, reflector, cladding, and engineering erials within the SNAP-2 core vessel. Values were denined for AISI Type 347 stainless steel, Hastelloy N, Zr, ZrH, and zirconium --uranium hydrides, from room temperature to temperatures greater than 1300 deg F. Derived equations were calculated for these materials, using a least squares analysis. Thermal expansion coefficients for the temperature range of 77 to 1200 deg F are: 10.34 x 10/sup 6/ in./ in./ deg F, for Type 347 stainless steel; 7.46 x 10/sup -6/ in./in./ deg F, for Hastelloy N; 9.07 x 10/sup ->/ in./ in./ deg F, for Be; and 6.12 x 10/sup -6/ in-/in./ deg F, for Zr--7 wt% UH with an N = 6.4. (auth)

Abstract: Hydrodynamic flow studies were conducted on a full scale model of the SM-2 reactor vessel and core. Test fluid was water at 200 psi and 200 degree F. Test facilities, model, and instrumentation design are discussed. Flow distribution in the stationary fuel elements, lattices, and control rods of the second pass was investigated. Pressure losses through the various core components were measured and are compared with calculated values. Observed over-all pressure drop was 71 feet of water at 200 degree F, 31% higher than predicted, part of which was due to presence of instrument leads. Element to element flow distribution varied approximately +-8% from pass average. Channel-to-channel stationary element flow distribution varied approximately +-10% from element average and control rod flow distribution varied from +-8.9% to +-6.4 and -11.6% depending upon rod locations. These variations exceed the original goals of a +-10% and +-12% combined deviation for stationary and control rod elements respectively, but are satisfactory in relation to thermal design. There was no indication of unsatisfactory structural performance of any components under hydrodynamic loadings up to 130% of design values. The test program was terminated after determining flow distribution in the reference core design, omitting any work on …