SNL-NJOY-2016

Nuclear data processing with enhanced version of the legacy NJOY-2016 code.

The NJOY-2016 code is an Open Source code, developed by LANL, and hosted on GitHub code repository. Sandia has made changes to the baseline NJOY-2016 code in order to support applications by the radiation damage community. The application area that our enhancements address are in the development of the energy-dependent radiation response functions for describing radiation damage to materials.

A typical application is iron embrittlement of the critical weld in the pressure vessel for a light water reactor. This energy dependent response permits the research community to correlate observed damage between exposures to the neutron environments in different reactors (typically comparison between commercial reactors and material test reactors). Thus, this enhanced code capability is useful to the academic community and the ASTM reactor pressure vessel embrittlement safety community.

We tried to incorporate our code changes into the current LANL Open Source version of NJOY-2016, but the NJOY code system has moved on to the NJOY21 code system and there were some compatibility issues with incorporating our required capability enhancements into the NJOY21 code. LANL has frozen their work on NJOY-2016. To distinguish our modified version of NJOY from the current LANL GitHub version, we are calling our code SNL-NJOY-2016 - and have also made our version available to the general public via GitHub. Our version includes our enhancements to the baseline LANL NJOY-2016 code using the Git software configuration control system - so configuration control between our version and LANL's version is rigorously maintained.
LANL (Jeremy Conlin) will examine these enhancements and try to find ways to incorporate our changes into a future LANL version of the NJOY21 code.

"Copyright 2020 National Technology & Engineering Solutions of Sandia, LLC (NTESS). Under the terms of Contract DE-NA0003525 with NTESS, the U.S. Government retains certain rights in this software."

                                             NOTICE:

For five (5) years from 6/11/2020 the United States Government is granted for itself and others acting on its behalf a paid-up, nonexclusive, irrevocable worldwide license in this data to reproduce, prepare derivative works, and perform publicly and display publicly, by or on behalf of the Government. There is provision for the possible extension of the term of this license. Subsequent to that period or any extension granted, the United States Government is granted for itself and others acting on its behalf a paid-up, nonexclusive, irrevocable worldwide license in this data to reproduce, prepare derivative works, distribute copies to the public, perform publicly and display publicly, and to permit others to do so. The specific term of the license can be identified by inquiry made to National Technology and Engineering Solutions of Sandia, LLC or DOE.

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Any licensee of this software has the obligation and responsibility to abide by the applicable export control laws, regulations, and general prohibitions relating to the export of technical data. Failure to obtain an export control license or other authority from the Government may result in criminal liability under U.S. laws.

This software has been assigned SCR# 2499.0. This number is an internal tracking number and is a useful reference when contacting the Legal Technology Transfer Center or Licensing and IP Management.

This software was originally assigned Export Control Classification Number (ECCN) EAR 99. However, since this software is to be released as OSS, the software is deemed to be Publicly Available.

Original NJOY README Information Below:

NJOY2016

The NJOY Nuclear Data Processing System is a modular computer code designed to read evaluated data in ENDF format, transform the data in various ways, and output the results as libraries designed to be used in various applications. Each module performs a well defined processing task. The modules are essentially independent programs, and they communicate with each other using input and output files, plus a very few common variables.

Documentation

The documentation for NJOY2016 is found in the NJOY2016-manual repository. There, you can find a pre-compiled PDF of the manual.

Installation

Instructions for the installation of NJOY2016 are found on our page, Obtaining and Installing NJOY.

Modules

• NJOY directs the flow of data through the other modules and contains a library of common functions and subroutines used by the other modules.
• RECONR reconstructs pointwise (energy-dependent) cross sections from ENDF resonance parameters and interpolation schemes.
• BROADR Doppler broadens and thins pointwise cross sections.
• UNRESR computes effective self-shielded pointwise cross sections in the unresolved energy range.
• HEATR generates pointwise heat production cross sections (KERMA coefficients) and radiation-damage cross sections.
• THERMR produces cross sections and energy-to-energy matrices for free or bound scatterers in the thermal energy range.
• GROUPR generates self-shielded multigroup cross sections, group-to-group scattering matrices, photon-production matrices, and charged-particle cross sections from pointwise input.
• GAMINR calculates multigroup photoatomic cross sections, KERMA coefficients, and group-to-group photon scattering matrices.
• ERRORR computes multigroup covariance matrices from ENDF uncertainties.
• COVR reads the output of ERRORR and performs covariance plotting and output formatting operations.
• MODER converts ENDF "tapes" back and forth between ASCII format and the special NJOY blocked-binary format.
• DTFR formats multigroup data for transport codes that accept formats based in the DTF-IV code.
• CCCCR formats multigroup data for the CCCC standard interface files ISOTXS, BRKOXS, and DLAYXS.
• MATXSR formats multigroup data for the newer MATXS material cross-section interface file, which works with the TRANSX code to make libraries for many particle transport codes.
• RESXSR prepares pointwise cross sections in a CCCC-like form for thermal flux calculators.
• ACER prepares libraries in ACE format for the Los Alamos continuous-energy Monte Carlo code MCNP.
• POWR prepares libraries for the EPRI-CELL and EPRI-CPM codes.
• WIMSR prepares libraries for the thermal reactor assembly codes WIMS-D and WIMS-E.
• PLOTR reads ENDF-format files and prepares plots of cross sections or perspective views of distributions for output using VIEWR.
• VIEWR takes the output of PLOTR, or special graphics from HEATR, COVR, DTFR, or ACER, and converts the plots into Postscript format for printing or screen display.
• MIXR is used to combine cross sections into elements or other mixtures, mainly for plotting.
• PURR generates unresolved-resonance probability tables for use in representing resonance self-shielding effects in the MCNP Monte Carlo code.
• LEAPR generates ENDF scattering-law files (File 7) for moderator materials in the thermal range. These scattering-law files can be used by THERMR to produce the corresponding cross sections.
• GASPR generates gas-production cross sections in pointwise format from basic reaction data in an ENDF evaluation. These results can be converted to multigroup form using GROUPR, passed to ACER, or displayed using PLOTR.

License and Copyright

This software is distributed and copyrighted according to the LICENSE file.