1. NAME AND TITLE
MUP2: A Program to Calculate Fast Neutron Data for Medium-Heavy Nuclei
Chinese Nuclear Data Center, Beijing, China, through NEA Data Bank, France.
3. CODING LANGUAGE AND COMPUTER
Fortran 77; IBM 3090.
4. NATURE OF PROBLEM SOLVED
MUP2 calculates fast neutron data for medium-heavy nuclei.
5. METHOD OF SOLUTION
The program includes the optical model, width fluctuation corrected Hauser-Feshbach formula and
pre-equilibrium statistical theory based on the exciton model. This code can calculate the cross
sections of all reaction channels, the elastic and inelastic scattering angular distributions for the discrete
states and secondary neutron spectra. The radial wave function in the optical model is solved by the
6. RESTRICTIONS OR LIMITATIONS
The calculations are restricted to medium-heavy nuclei, for which the fission reactions are absent.
The maximum number of the isotopes of the target nucleus is limited to six. The energy region for
incident neutrons is .01 to 20 MeV. The maximum number of energy points of outgoing secondary
neutrons is 100.
7. TYPICAL RUNNING TIME
The sample input was tested at RSIC on the IBM 3090 under the MVS operating system. The
problem took 11.98 seconds. Compilation of MUP2 was 19.74 seconds. Linking took .77 seconds.
8. COMPUTER HARDWARE REQUIREMENTS
MUP2 runs on the IBM 3090.
9. COMPUTER SOFTWARE REQUIREMENTS
The code was written in Fortran 77 and requires the VS Fortran compiler (version 2.2.0 was used
Su Zong Di and P. E. Hodgson, "Comparison Between Chinese Unified Program (MUP2) and
International Nuclear Model Programs," IAEA0907/03 (May 4, 1988).
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: CROSS SECTION PROCESSING; NEUTRON; PARAMETRIC MODELS