1. NAME AND TITLE
ENTOSAN: Code System for Calculating Fine-Group Dosimetry Cross Section Values from
Netherlands Energy Research Foundation ECN, Petten, The Netherlands through the NEA Data
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
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
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.
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