A method is described how a quantitative measure for the robustness of a given transport theory code for coarse network calculations can be obtained. A code, that performs this task automatically and at only nominal cost, is described and has been implemented for slab geometry. This code generates also user oriented benchmark problems which exhibit the analytic behavior at interfaces.

Two modeling programs, SCEPTRE and CSMP, are used to solve the point-kinetics equations - - seven coupled nonlinear differential equations - - with a linear-feedback function. The constants used are appropriate for EBR-II; therefore the computational accuracy may be tested against the experimental rod drops. Run-time, versatility, programming ease, and accuracy are criteria used to evaluate the two programs. SCEPTRE is found to be more efficient in run time and CSMP more versatile. The ease of programming is about the same for both programs. The accuracy is nearly equivalent if the optimum integration routines are used.

Ultrasonic inspection of large-grain stainless steel and stainless steel welds is difficult, and the results obtained are not easily interpreted. In the present study, the effects of stainless steel microstructure on ultrasonic test results are described, and several signal-processing techniques for enhancing ultrasonic flaw signals are discussed.

Technology utilization/commercialization is the process of applying technology to satisfy a preexisting need. The present report examines the organizational relationships involved, the controlling factors, and the role of the technology agent. Included is a brief assessment of the technology commercialization activities currently under way as part of specific research and development projects at Argonne National Laboratory. In addition to the usual supporting references, an appendix is devoted to a sampling of the relevant literature.

The reactor physics studies performed in the gas cooled fast reactor (GCFR) mockup on ZPR-9 are covered. This critical assembly, designated Phase II in the GCFR program, had a single zone PuO₂-UO₂ core composition and UO₂ radial and axial blankets. The assembly was built both with and without radial and axial stainless steel reflectors. The program included the following measurements: small-sample reactivity worths of reactor constituent materials (including helium); ²³⁸U Doppler effect; uranium and plutonium reaction rate distributions; thorium, uranium, and plutonium alpha and reactor kinetics. Analysis of the measurements used ENDF/B-IV nuclear data; anisotropic diffusion coefficients were used to account for neutron streaming effects. Comparison of measurements and calculations to GCFR Phase I are also made.