Computer Programs
NEA-1907 FRENDY.
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NEA-1907 FRENDY.

FRENDY, Nuclear Data Processing System for Evaluated Nuclear Data File

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1. NAME OR DESIGNATION OF PROGRAM

FRENDY Version 1.

 

FRENDY is freely available at https://rpg.jaea.go.jp/main/en/program_frendy/

 

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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
FRENDY NEA-1907/01 Report 27-SEP-2019

Machines used:

Package ID Orig. computer Test computer
NEA-1907/01 MAC,Linux-based PC,PC Windows
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3. DESCRIPTION OF PROGRAM OR FUNCTION

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.

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4. METHODS

FRENDY version 1 generates an ACE file from evaluated nuclear data file. The detail of the processing methods to generate an ACE file are documented in JAEA-Data/Code2018-014.

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6. TYPICAL RUNNING TIME

FRENDY prepares sample cases to generate ACE file. All 15 sample input files ran in about 15 minutes on Intel Xeon Gold 6154 (3.00GHz) without parallel computation.

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7. UNUSUAL FEATURES OF THE PROGRAM

FRENDY has the following unusual capabilities:

  • Perturbation of ACE file with perturbation_ace_file.exe.

  • Random sampling of ACE file with make_perturbation_factor.

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8. RELATED OR AUXILIARY PROGRAMS
  • perturbation_ace_file: Program to perturb an ACE file when user sets the ACE file name, reaction type, energy region, and amount of perturbation.

  • make_perturbation_factor: Program for uncertainty analysis using the random sampling method for ACE file.

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9. STATUS
Package ID Status date Status
NEA-1907/01 27-SEP-2019 Report Only
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10. REFERENCES
  • 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).

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11. HARDWARE REQUIREMENTS

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.

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1907/01 C++
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13. SOFTWARE REQUIREMENTS

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.

 

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15. NAME AND ESTABLISHMENT OF AUTHORS

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

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16. MATERIAL AVAILABLE
NEA-1907/01
README file
frendy : Source files of FRENDY
tests  : Source files to run the Boost. Test library for verification
sample : Input files for the test calculations
tools  : Tools which use FRENDY modules.
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems

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.