1. NAME AND TITLE
CRECTJ5: A Computer Program for Compilation of Evaluated Nuclear Data in ENDF/B
Japan Atomic Energy Research Institute, Tokai-Mura, Naka-Gun, Ibaraki-Ken, Japan, through the
NEA Data Bank, Gif-sur-Yvette, France.
3. CODING LANGUAGE AND COMPUTER
4. NATURE OF PROBLEM SOLVED.
CRECTJ5 can be used to compile evaluated nuclear data in ENDF/B-IV and ENDF/B-V formats.
Its predecessor, CRECTJ, was used to compile evaluated for the Japanese Evaluated Nuclear Data File
(JENDL-1 and -2), both of which were in ENDF/B-IV format. When work began on the third
version, in ENDF/B-V format, modifications were made to accommodate the new format and the name
was changed to CRECTJ5. Its main function is in reading evaluated nuclear data and making a
complete and consistent file that conforms to the format rules. In addition, it can be used for
performing arithmetic operations, averaging, and correcting cross sections, and constructing natural
element data from isotopic data.
5. METHOD OF SOLUTION
CRECTJ5 reads evaluated data by specifying the MAT, MF and MT numbers. The data read into CRECTJ5 are stored on scratch disks in binary form. Four arithmetic operations, addition, subtraction, multiplication and division of cross-section data can be done. Hence the total cross section can be calculated from other partial cross sections. Some special quantities such as cross-section ratios or discrepancies between two cross-section data can also be calculated.
Segments of an evaluated data set can be replaced with data from another or corrected by inserting new data points.
Natural element data can be constructed from its isotopic components, but this is limited to resonance parameters, cross-section data, and angular distributions of elastically scattered neutrons, in the present version of CRECTJ5.
Renormalization of cross sections can be done by supplying a multiplying factor. For tabulated angular-distribution data, normalization to unity can be performed.
Results are written in ENDF/B-IV or ENDF/B-V format with a new MAT number with data sorted
in increasing order of MF and MT numbers. A dictionary in MF=1, MT=451 is automatically
created. Energy values of cross-section data can be written in six-, seven-, or nine-digit format.
6. RESTRICTIONS OR LIMITATIONS
7. TYPICAL RUNNING TIME
The following CPU times were required for the sample test cases included in this code package:
Case 1, 21 seconds
Case 2, 83 seconds
Case 3, 17 seconds
Case 4, 41 seconds.
8. COMPUTER HARDWARE REQUIREMENTS
CRECTJ5 runs on a VAX 11/780 computer. For the sample problems, a peak working set size
of 925 pages was required.
9. COMPUTER SOFTWARE REQUIREMENTS
The sample problems in this package were run with a VMS 4.4 Operating System. Included are
calls to the clock routine CLOCKM to time program performance. These calls may need to be
replaced by similar calls to a VAX clock routine SECNDS.
T. Nakagawa "CRECTJ5, A Computer Program for Compilation of Evaluated Nuclear Data in the
ENDF/B Format," Informal Document (1986).
11. CONTENTS OF CODE PACKAGE
Included is the referenced document and one (1.2MB) DOS diskette which contains the source
code, sample problem input and output.
12. DATE OF ABSTRACT
KEYWORDS: CROSS SECTION PROCESSING; DATA CHECKING; ENDF FORMAT; ENDF/B-V