Program name | Package id | Status | Status date |
---|---|---|---|
FRENDY | NEA-1907/01 | Tested | 13-NOV-2019 |
Machines used:
Package ID | Orig. computer | Test computer |
---|---|---|
NEA-1907/01 | MAC,Linux-based PC,PC Windows | Linux-based PC,PC Windows |
FRENDY (FRom Evaluated Nuclear Data librarY to any application) is a nuclear data processing system to generate a cross-section file from evaluated nuclear data file. FRENDY supports recent evaluated nuclear data libraries (e.g., JENDL-3.3 and JENDL-4.0 in Japan, ENDF-B/VII.1 and ENDF-B/VIII.0 in the US, JEFF-3.2 and JEFF-3.3 in Europe). FRENDY version 1 generates an ACE file which is the cross section file for continuous energy Monte Carlo calculation codes.
Features of FRENDY are as follows:
Two types of input formats (Simple input format and NJOY compatible format)
FRENDY accepts two types of input formats.
The simple input format requires only the processing mode and evaluated nuclear data file name at minimum. This input format does not require the expertise of the nuclear data processing. The other input parameters are automatically set from the evaluated nuclear data file. User can also specify the parameters in the input file if they want to change them.
FRENDY has an alternative capability of reading ordinary NJOY inputs without any modifications. Many users process the evaluated nuclear data file with NJOY. They can easily use FRENDY without changing the input files for NJOY. They can therefore replace NJOY modules with FRENDY ones as they need. In addition, the modules of FRENDY and NJOY can be used in combination. For example, users can generate the multi-group cross-section data library using the GROUPR module of NJOY with the PENDF file generated by FRENDY. Available NJOY modules in FRENDY are RECONR (resonance reconstruction and linearization), BROADR (Doppler broadening), GASPR (calculation of gas production cross-section), PURR (generation of probability table), UNRESR (calculation of Bondarenko-type self-shielded cross-section), THERMR (calculation of thermal scattering cross-section), ACER (generation of ACE file), and MODER (modification of PENDF file).
Extensible & Modular
FRENDY is developed not only to process evaluated nuclear data files but also to apply the modules to other codes. FRENDY is written in C++ and all the modules are encapsulated. Users can easily employ many functions (e.g., read, write, and process an evaluated nuclear data file) in their own codes when they implement the classes of FRENDY to their codes.
Open source software under 2-clause BSD license
There is no restriction to introduce the FRENDY modules into other codes.
FRENDY is freely available at https://rpg.jaea.go.jp/main/en/program_frendy/
Some introduction articles are also published in this website.
K. Tada, Y. Nagaya, S. Kunieda, K. Suyama, T. Fukahori, "Development and verification of a new nuclear data processing system FRENDY," J. Nucl. Sci. Technol., 54, pp.806-817 (2017).
K. Tada, S. Kunieda, Y. Nagaya, “Nuclear data processing code FRENDY version 1,” JAEA-Data/Code 2018-014 (2019).
FRENDY runs on various platforms such as Linux, Windows, and Mac. Disk space of about 1.5Gbytes is required to compile FRENDY and run all sample programs. To compile FRENDY, Disk space of 250Mbyte is required.
Tested at the NEA Data Bank on:
COMPUTER: Dell Precision M6800 with Intel(R) Core (TM) i7-4800MQ CPU at 2.70 GHz x 8, RAM: 16.0 GB
OPERATING SYSTEM: Ubuntu 18.04
GCC ver. 7.4
COMPUTER: Intel(R) Core (TM) i7-4770 CPU at 3.40 GHz x 4, RAM: 8.0 GB
OPERATING SYSTEM: Windows 10 Enterprise
GCC ver. 8.1
FRENDY runs on the following operation systems: Linux, Windows, and Mac.
The supported C++ compilers are Intel compiler and GNU compiler.
BOOST and LAPACK libraries are required to compile FRENDY.
Matrix calculation library Eigen is required to compile related program make_perturbation_factor.
Kenichi TADA, Satoshi KUNIEDA, Yasunobu NAGAYA
Research Group for Reactor Physics and Standard Nuclear Code System
Nuclear Data and Reactor Engineering Division
Nuclear Science and Engineering Center
Sector of Nuclear Science Research
Japan Atomic Energy Agency
Tokai-mura, Naka-gun, Ibaraki
Japan
Keywords: ACE, ENDF, ENDF-B/VII.1, ENDF-B/VIII.0, JEFF, JEFF-3.2, JEFF-3.3, JENDL, JENDL-3.3, JENDL-4.0, cross sections, data library, data processing, evaluated nuclear data, nuclear data, open-source code.