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Development of a Nuclear Data Processing Code FRENDY Version 1

Nuclear data processing is an important interface between an evaluated nuclear data library and nuclear transport calculation codes. The Japan Atomic Energy Agency develops a new nuclear data processing code FRENDY in order to process the evaluated nuclear data library JENDL. The current version of FRENDY can generate ACE formatted files for continuous energy Monte Carlo calculation codes such as PHITS and MCNP. It uses the same processing method as NJOY because the implementation of the conventional method is an important step to develop the new code. FRENDY is coded so as to enhance maintainability, modularity, portability and flexibility. FRENDY is written in the object-oriented language C++ to achieve these requirements. The maintainability and modularity are better than the conventional codes written in FORTRAN. Each module is designed to be compact and independent for portability and flexibility. FRENDY is developed not only to process evaluated nuclear data libraries but also to apply the FRENDY modules to other calculation codes. Users can easily use many modules in FRENDY when they add a few lines in their code.