1. NAME AND TITLE
NJOY91.119: Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
UPD 1.3: Portable Update Emulator.
Los Alamos National Laboratory, Los Alamos, New Mexico.
3. CODING LANGUAGE AND COMPUTER
Fortran 77; Cray, VAX, Sun and IBM RS/6000 workstations. (P00171/MFMWS/04).
4. NATURE OF PROBLEM SOLVED
The NJOY nuclear data processing system is a comprehensive computer code package for producing pointwise and multigroup neutron and photon cross sections from ENDF/B evaluated nuclear data. This is the last NJOY-91 series. It uses the same module structure as the earlier versions and its graphics options depend on DISSPLA. This new release, designated NJOY91.119, includes bug fixes, improvements in several modules, and some new capabilities. Information on the changes is included in the README file. A new test problem was added to test some ENDF-6 features, including Reich-Moore resonance reconstruction, energy-angle matrices in GROUPR, and energy-angle distributions in ACER. The 91.119 release is basically configured for UNIX.
5. METHOD OF SOLUTION
For the NJOY87 release, the code was changed from a CDC "overlay" structure to a "segment" type structure that is more compatible with IBM and Cray. All modules are now "subroutines", and no OVERLAY or CALL OVERLAY statements are used. Some of the included modules in NJOY91 are:
NJOY The driver program
RECONR Reconstructs pointwise data from resonance parameters
BROADR Doppler broadens and thins pointwise data
UNRESR Calculates effective self-shielded pointwise cross sections in the unresolved-resonance region
HEATR Calculates pointwise KERMA factors and damage cross sections
THERMR Produces thermal scattering matrices
GROUPR Generates self-shielded multigroup cross sections, neutron scattering matrices, and photon production matrices from pointwise input
GAMINR Calculates multigroup photon interaction cross sections, KERMA factors, and photon scattering matrices
ERRORR Produces multigroup covariance matrices from ENDF/B uncertainty files
COVR Plots and performs output operations on ERRORR files
MODER Converts blocked binary files to/from formatted form
DTFR Formats multigroup data for use in transport codes
CCCCR Formats multigroup data into CCCC interface forms
MATXSR Formats multigroup data into MATXS interface forms
ACER Prepares libraries for MCNP
PLOTR Plots 2-d graphs of ENDF, PENDF, or GENDF data.
6. RESTRICTIONS OR LIMITATIONS
7. TYPICAL RUNNING TIME
Sample problem execution times follow:
CRAY Sun Sparc Station 2
IN1: natural carbon; 118 sec. 430.9 sec.
IN2: Pu-238; 125 sec. 349.5 sec.
IN3: H, U photon interaction; 44 sec. 141.2 sec.
IN4: U-235 uncertainty file; 10 sec. 44.9 sec.
IN5: 153 sec. 424.2 sec.
IN7: 59 sec. 231.9 sec.
8. COMPUTER HARDWARE REQUIREMENTS
NJOY91 runs on Cray computers. Specialized updates are included for VAX, Sun workstations, and IBM RS/6000.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran 77 compiler is required. The CFT77 compiler was used under UNICOS. RSIC tested this release on a Sun running SUN OS 4.1.1 using the Fortran 1.4 compiler. NJOY91 uses DISSPLA graphics software available from ISSCO. Omit the '*set diss' upd command if DISSPLA is not available on your system. This system runs on Cray under either UNICOS or CTSS, on the VAX under VMS, on the Sun under either Sun OS4 or OS5, and on IBM RS/6000 under AIX 3.2.5.
R. E. MacFarlane and D. W. Muir, "The NJOY Nuclear Data Processing System Version 91," LA-12740-M (October 1994).
R. E. MacFarlane and D. C. George,"UPD: A Portable Version-Control Program," LA-12057-MS (April 1991).
R. E. MacFarlane, "How to NJOY ENDF-6," The International Workshop on NJOY, Saclay, France (April 1992).
11. CONTENTS OF CODE PACKAGE
Included are the referenced documents and the NJOY91 and UPD source codes, updates, jcl files, selected ENDF/B data sets, sample problem input and output. The package is available on either a DC6150 tape cartridge (150 MB) or 8mm tape in tar format. Version 91.119 updates only are available on 1 DS/HD (1.2 MB) diskette in self-extracting DOS compressed files.
12. DATE OF ABSTRACT
April 1984; revised November 1987, July 1989, October 1989, January 1990, May 1990, August 1991, September 1991, July 1992, June 1993, October 1993, December 1994, and June 1995.
KEYWORDS: COVARIANCE DATA PROCESSING; ENDF/B-V; ENDF FORMAT; GAMMA-RAY CROSS SECTION PROCESSING; GAMMA-RAY PRODUCTION CROSS SECTION PROCESSING; KERMA; MULTIGROUP CROSS SECTION PROCESSING; NEUTRON CROSS SECTION PROCESSING; WORKSTATION