NEA-0948 CRECT-J.

CRECT-J, Input Preparation of Evaluated Data in ENDF-4, ENDF-5 and ENDF-6 Formats

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, CPU, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: CRECT-J5 and CRECT-J6.

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.

Program name	Package id	Status	Status date
CRECT-J5	NEA-0948/01	Tested	30-JUN-1987
CRECT-J6	NEA-0948/03	Tested	30-OCT-2000

Machines used:

Package ID	Orig. computer	Test computer
NEA-0948/01	FACOM M-200	DEC VAX 11/780
NEA-0948/03	FACOM M200	PC Windows,Linux-based PC,IBM RISC6000 WS

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3. DESCRIPTION OF PROGRAM OR FUNCTION

In order to compile evaluated nuclear data in the ENDF format, the computer code CRECTJ has been developed. CRECTJ has two versions: CRECT-J5 treats the data in the ENDF/B-IV and ENDF/B-V format, and CRECTJ6 the data in the ENDF-6 format. These programs have been frequently used to make Japanese Evaluated Nuclear Data Library (JENDL).
The program has functions for reading evaluated nuclear data and creating complete files from them. In addition, it also has functions such as arithmetic operations on cross section data, averaging of cross sections, correction of data, and construction of natural element data from its isotopes.

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4. METHOD OF SOLUTION:

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

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6. TYPICAL RUNNING TIME

NEA-0948/01

NEA-DB executed the test cases included in this package on a VAX-11/780 computer. The following CPU times were required: 21 seconds (case 1); 83 seconds (case 2); 17 seconds (case 3); 41 seconds (case 4).

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7. UNUSUAL FEATURES OF THE PROGRAM:

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8. RELATED AND AUXILIARY PROGRAMS:

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9. STATUS

Package ID	Status date	Status
NEA-0948/01	30-JUN-1987	Tested at NEADB
NEA-0948/03	30-OCT-2000	Tested at NEADB

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10. REFERENCES:

NEA-0948/01, included references:

- T. Nakagawa:
CRECTJ5 (Version 84-08): A Computer Program for Compilation of
Evaluated Nuclear Data in the ENDF/B Format

NEA-0948/03, included references:

- Tsuneo Nakagawa:
CRECTJ: A Computer Program for Compilation of Evaluated Nuclear Data
JAERI-Data/Code 99-041 (September 1999)

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11. MACHINE REQUIREMENTS:

NEA-0948/01

Three scratch tapes are used. For execution of the test cases in a VAX-11/780, a peak working set size of 925 pages was required.

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
NEA-0948/01	FORTRAN-IV
NEA-0948/03	FORTRAN-77

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

NEA-0948/01

VMS 4.4 (VAX-11/780).

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

NEA-0948/01

The included calls to the clock routine CLOCKM to time program performance had to be replaced by similar calls to a VAX clock routine SECNDS.

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15. NAME AND ESTABLISHMENT OF AUTHORS

          T. NAKAGAWA
          Japan Atomic Energy Institute
          Department of Physics
          Tokai Research Establishment
          JAPAN

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16. MATERIAL AVAILABLE

NEA-0948/03

CRECTJ6.F Fortran source code
JCL for test case 1
First input file for test case 1
Second input file for test case 1
Third input file for test case 1
Output file for test case 1
Report file for test case 1
JCL for test case 2
Input file for test case 2
Output file for test case 2
Report file for test case 2
JCL for test case 3
First input file for test case 3
Second input file for test case 3
Output file for test case 3
Report file for test case 3
JCL for test case 4
First input file for test case 4
Second input file for test case 4
Output file for test case 4
Report file for test case 4

NEA-0948/01

File name	File description	Records
NEA0948_01.001	Information file	80
NEA0948_01.002	CRECT-J5 Fortran source file	8094
NEA0948_01.003	JCL for test case 1	31
NEA0948_01.004	First input file for test case 1	475
NEA0948_01.005	Second input file for test case 1	155
NEA0948_01.006	Third input file for test case 1	13
NEA0948_01.007	Output file for test case 1	758
NEA0948_01.008	Report file for test case 1	155
NEA0948_01.009	JCL file for test case 2	14
NEA0948_01.010	Input file for test case 2	14831
NEA0948_01.011	Output file for test case 2	320
NEA0948_01.012	Report file for test case 2	100
NEA0948_01.013	JCL file for test case 3	20
NEA0948_01.014	First input file for test case 3	82
NEA0948_01.015	Second input file for test case 3	393
NEA0948_01.016	Output file for test case 3	327
NEA0948_01.017	Report file for test case 3	71
NEA0948_01.018	JCL file for test case 4	25
NEA0948_01.019	First input file for test case 4	1382
NEA0948_01.020	Second input file for test case 4	1691
NEA0948_01.021	Output file for test case 4	990
NEA0948_01.022	Report file for test case 4	327

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17. CATEGORIES

M. Data Management

Keywords: ENDF/B, cross sections, evaluated data, neutron cross sections.