1. NAME AND TITLE
ENBAL2: A Program to Generate Multigroup Neutron Kerma Factors.
ENBAL2 is a development from an earlier program, ENBAL, which employs a greater flexibility
of use of available cross sections, improved efficiency in data handling, and revised treatment of
inelastic scattering to the continuum.
University of Birmingham, Birmingham, England.
3. CODING LANGUAGE AND COMPUTER
Fortran IV; IBM 370, 3033.
4. NATURE OF PROBLEM SOLVED
ENBAL2 generates multigroup neutron and gamma-ray kerma factors from multigroup cross
sections. It has a number of options for the format of output of the kerma factors, including formats
enabling direct use of the values in transport codes such as ANISN.
5. METHOD OF SOLUTION
In order to obtain an expression for the kerma factor, ENBAL2 considers the rate of energy deposition in four types of neutron interaction: elastic scattering, inelastic scattering, charged particle producing reactions such as (n,p) and radiative capture. Multigroup kerma factors are computed directly from multigroup neutron cross sections, provided sufficient partial cross section data is available, together with reaction Q-values and inelastic level energies.
Energy deposition by neutrons in each energy group is obtained by considering the total energy
balance for each reaction type. For inelastic scattering to the continuum, unless a partial group-to-group transfer matrix is available, excitation of the residual nucleus is modeled by an evaporation
6. RESTRICTIONS OR LIMITATIONS
7. TYPICAL RUNNING TIME
No study has been made by RSIC of typical running times for ENBAL2.
8. COMPUTER HARDWARE REQUIREMENTS
ENBAL2 is operable on the IBM 370 or IBM 3033 computers.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran IV compiler is required.
N. P. Taylor, "ENBAL2, A Programme to Generate Multigroup Neutron Kerma Factors."
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and one (1.2MB) DOS diskette which contains the source
code and sample problem input and output.
12. DATE OF ABSTRACT
KEYWORDS: CROSS SECTION PROCESSING; GAMMA-RAY CROSS SECTION PROCESSING; MULTIGROUP CROSS SECTION PROCESSING; NEUTRON CROSS SECTION PROCESSING