1. NAME AND TITLE
KAOS-V: An Evaluation Tool For Neutron Kerma Factors And Other Nuclear Responses
Argonne National Laboratory, Argonne, Illinois.
3. CODING LANGUAGE AND COMPUTER
Fortran 77; Cray computers.
4. NATURE OF PROBLEM SOLVED
KAOS-V evaluates accurately the neutron fluence-to-kerma factors from microscopic nuclear data.
5. METHOD OF SOLUTION
Two basic methods for computing kerma factors, namely kinematics and energy balance, are implemented in KAOS-V. KAOS-V uses data from the evaluated nuclear data files ENDF/B-V. Auxiliary nuclear data bases, such as the Japanese evaluated nuclear data library JENDL-2 can be used as a source of isotopic cross sections. These are needed to estimate average quantities such as effective Q-values for the natural element. For resonance treatment, the code has the ability to access NJOY and NPTXS interface files in formatted or binary forms.
6. RESTRICTIONS OR LIMITATIONS
7. TYPICAL RUNNING TIME
The sample problem took about 1.5 minutes on the Cray.
8. COMPUTER HARDWARE REQUIREMENTS
The code runs on the Cray computers.
9. COMPUTER SOFTWARE REQUIREMENTS
The code was written in Fortran 77 under the CTSS operating system. The CFT compiler is used. The plotting routines require the DISSPLA graphics system.
Y. Farawila, Y. Gohar, and C. Maynard. KAOS-V Code: An Evaluation Tool For Neutron Kerma Factors and Other Nuclear Responses, ANL/FPP/TM-240, Argonne National Laboratory, Argonne, Illinois, September 1989.
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and one DS/DD (360 K) 5.25 inch diskette.
12. DATE OF ABSTRACT
KEYWORDS: INTERACTIVE, ON-LINE; KERMA; NEUTRON