Validation of MCNP, a comparison with SCALE: Part 2, Highly enriched uranium metal systems.

摘要

This is Part 2 of a series of validation studies dealing with highly enriched uranium systems. For this study six sets of critical experiments involving uranium metal have been modeled and an effective multiplication factor, k(sub eff), calculated for each experiment. An earlier study(sup 1) addresses the validation of MCNP for use with highly enriched uranium solutions. The calculations of k(sub eff) were performed using MCNP 4. MCNP is a Monte Carlo based transport code which used continuous energy nuclear data for these calculations. END/B-V cross sections were used for this study- This report also compares the results of MCNP with the results of the CSAS25 module of SCALE 4 using the 27 group END/B-IV cross sections. Provided in Section 2 are general descriptions of the experiments performed. Section 3, Results, consists primarily of tables listing the calculated K(sub eff)'s. Lastly, Sections 4 and 5 give a general discussion of observed trends in the results and suggested biases.