Benchmark problems in nuclear data processing and utilization system for innovative reactors

A nuclear data processing and utilization system has been developed for research and development of innovative reactors such as accelerator-driven systems. The system is able to handle JENDL-3.3, ENDF/B-VI, and JEFF-3.1 to generate pointwise and groupwise cross sections in several formats, and has a capability to perform criticality and shielding benchmarks. Verification of nuclear data is available by using various criticality and shielding benchmark problems selected from database such as ICSBEP and SINBAD. The system performance highly depends on the quality of benchmark problems so that appropriate benchmarks should be selected from existing database. However a number of adequate benchmarks are quite a few to verify nuclear data for application of the accelerator-driven systems. Hence that new measurement should be necessary concerning criticality and shielding benchmarks. In the JENDL high-energy file (JENDL/HE) project, the intermediate-energy nuclear data integral test working group of Japanese Nuclear Data Committee made critical review of existing benchmark problems for accelerator-driven systems and performed verification of nuclear data in JENDL/HE. In this paper, the scheme of benchmark procedure and the selected benchmarks in the nuclear data processing and utilization system have been described