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