학술논문

Development of a Nuclear Data Processing Code FRENDY Version 1
Document Type
Conference
Source
2019 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC) Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC), 2019 IEEE. :1-2 Oct, 2019
Subject
Bioengineering
Components, Circuits, Devices and Systems
Computing and Processing
General Topics for Engineers
Nuclear Engineering
Photonics and Electrooptics
Power, Energy and Industry Applications
Robotics and Control Systems
Signal Processing and Analysis
Libraries
Data processing
Nuclear power generation
Monte Carlo methods
Doppler effect
Neutrons
Uncertainty
evaluated nuclear data
FRENDY
nuclear data processing
Language
ISSN
2577-0829
Abstract
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.