Integrated nuclear data utilization system for innovative reactors nuclear data processing and utilization system

Abstract

A nuclear data processing and utilization system has been developed as a modular code system of the integrated nuclear data utilization system for innovative nuclear energy systems. The system was developed in part of the research project entitled Fundamental Research and Development (R&D) on Neutron Cross Sections for Innovative Reactors using Advanced Radiation Measurement Technology. The system is able to handle evaluated nuclear data in the ENDF-6 format to generate point-wise and group-wise cross sections in several formats, and has a capability to perform criticality and shielding benchmarks based on various criticality and shielding benchmark problems selected from database such as ICSBEP and SINBAD. The system is operated with a common graphical interface (CGI) in order to easily utilize the system through Internet for not only nuclear design engineers but also nuclear data evaluators. The system is expected to apply quality assurance program for the JENDL-4 project. An overview of the integrated nuclear data utilization system and the scheme of cross section generation and benchmark procedure in the system have been described as well as future development plan based on the system.