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RSIC CODE PACKAGE PSR-188


1. NAME AND TITLE

ENTOSAN: Code System for Calculating Fine-Group Dosimetry Cross Section Values from ENDF/B Data.

2. CONTRIBUTOR

Netherlands Energy Research Foundation ECN, Petten, The Netherlands through the NEA Data Bank, France.

3. CODING LANGUAGE AND COMPUTER

Fortran IV EXTENDED; CDC-CYBER 175 (P00188C017500), VAX (P00188D881000).

4. NATURE OF PROBLEM SOLVED

ENTOSAN calculates multigroup cross section values for a fine-group structure from data in the ENDF/B format.

5. METHOD OF SOLUTION

ENTOSAN calculates the group cross sections for a fine-group structure directly (i.e., without the calculation of point cross section data) in a fixed energy pattern for the complete energy range of interest. The resonance contributions are treated in a sequential way, so that only the parameters for one resonance need storage in the central memory of the computer. A constant neutron spectrum is used implicitly in the program. It is assumed that a group structure of the CCC-112/SAND-II type with 640 groups covering the energy range from 10-10 to 20 MeV applied in the program is a suitable fine group structure for the purpose of neutron spectrum unfolding.

6. RESTRICTIONS OR LIMITATIONS

None noted.

7. TYPICAL RUNNING TIME

A simple (n,p) reaction required 1 sec CPU time on a CDC CYBER 175 computer.

A complicated (n,f) reaction required 16 sec CPU time on a CDC CYBER 175 computer.

8. COMPUTER HARDWARE REQUIREMENTS

ENTOSAN is operable on a CDC CYBER 175 computer using a NOS/BE operating system. Approximately 31000 computer words of memory are needed for execution of the program. VAX family under VAX/VMS.

9. COMPUTER SOFTWARE REQUIREMENTS

A Fortran IV EXTENDED compiler is required for CDC version. Fortran 77 for VAX under the VMS Operating System.

10. REFERENCE

H. Ch. Rieffe, H. J. Nolthenius, and W. L. Zijp, "ENTOSAN--A Program for the Calculation of Fine Group Cross Section Values from ENDF/B Data," ECN-93 (April 1981).





11. CONTENTS OF CODE PACKAGE

Included are the referenced document and one (1.2MB) DOS diskette which contains the source code, ENDF/B-V library for the sample problem, and sample problem input and output.

12. DATE OF ABSTRACT

July 1982; revised October 1983; reviewed May 1984, September 1993.

KEYWORDS: ENDF FORMAT; ENDF/B-V; MULTIGROUP CROSS SECTION PROCESSING; NEUTRON CROSS SECTION PROCESSING