Re-evaluations for SINBAD Experiments Using ENDF/B-VII, JEFF-3.1, and JENDL-3.3

Abstract

SINBAD (Shielding Integral Benchmark Archive Database) started in 1996 as a joint project of the OECD/NEA Data Bank (Organization for Economic Cooperation and Development, Nuclear Energy Agency Data Bank) and ORNL/RSICC (Oak Ridge National Laboratory, Radiation Safety Information Computational Center). It contains a variety of experiments concerning reactor shielding, fusion blanket neutronics, and accelerator shielding that are useful to verify and validate radiation shielding codes as well as nuclear data libraries. In this work, re-evaluation of SINBAD experiments has been conducted by using the MCNPX code with recently released nuclear data libraries, ENDF/B-VII, JEFF-3.1, and JENDL-3.3. The MCNPX calculations for several typical problems of SINBAD reactor shielding, fusion neutronics, and accelerator shielding were carried out and validated through comparing with available experimental data. It is found that there was reasonable agreement between the calculational and experimental results. Hence, ENDF/B-VII, JEFF-3.1, and JENDL-3.3 are strongly recommended to be used for validating the new developed radiation shielding methods and codes.