IAEA1177 UNIFY.

UNIFY, Fast Neutron Cross-Sections and Spectrum for Structural Materials

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

[ top ]

1. NAME OR DESIGNATION OF PROGRAM: UNIFY.

[ top ]

2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.

Program name	Package id	Status	Status date
UNIFY	IAEA1177/01	Arrived	19-JAN-2000

Machines used:

Package ID	Orig. computer	Test computer
IAEA1177/01	CDC CYBER 825

[ top ]

3. DESCRIPTION OF PROGRAM OR FUNCTION

Based on the unified model, the code UNIFY calculates fast neutron data for structural materials:
(1) Cross sections - Total cross sections for all types of reaction  channels; cross sections of discrete level and continuum emissions.
(2) Angular distribution - elastic scattering angular distributions  and its Legendre coefficients and transition matrix elements; Legendre coefficients of discrete levels in the inelastic scattering channels.
(3) Energy spectra
(4) Double differential cross sections of the inelastic and neutron  outgoing channels.

[ top ]

4. METHOD OF SOLUTION

Gaussian integration is used for all numerical integrations.

[ top ]

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

UNIFY can be used for neutron incident energies from 1 KeV to 20 MeV. Due to main storage limitations the number of incident energies could not exceed 50.

[ top ]

6. TYPICAL RUNNING TIME

For En = 14 MeV: 200 seconds; En = 20 MeV: 500 seconds of CPU time were required. At lower energies, the calculations are quite fast.

[ top ]

7. UNUSUAL FEATURES OF THE PROGRAM: Several calculational and output options are available.

[ top ]

8. RELATED AND AUXILIARY PROGRAMS:

[ top ]

9. STATUS

Package ID	Status date	Status
IAEA1177/01	19-JAN-2000	Masterfiled Arrived

[ top ]

10. REFERENCES:

IAEA1177/01, included references:

- Zhang Jingshang and Shi Xiangjun:
  The Formuation of "UNIFY" Code for the Calculation of Fast Neutron
  Data for Structural Materials
  INDC(CPR)-014/LJ (January 1989)
- Shi Xiangjun ans Zhang Jingshang:
  Description of UNIFY-ECN Code and the Guide for Users.

[ top ]

11. MACHINE REQUIREMENTS:

[ top ]

12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
IAEA1177/01	FORTRAN-77

[ top ]

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

Extended memory may be used with: RFL EC=400. Depending on available storage, the parameters NEL and NLP may be set.

[ top ]

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

[ top ]

15. NAME AND ESTABLISHMENT OF AUTHORS

         Shi Xiangjun and Zhang Jingshang
         Chinese Nuclear Data Center
         Institute of Atomic Energy
         P.O. Box 275 (41)
         BEIJING 102413
         P. R. China

[ top ]

16. MATERIAL AVAILABLE

IAEA1177/01

source program   mag tapeUNIFY Source Program                       SRCTP
test-case data   mag tapeUNIFY Input Data                           DATTP
test-case output mag tapeUNIFY Output Data                          OUTTP
test-case data   mag tapeInput + Output Data                        DATTP
miscellaneous    mag tapeAbstract                                   MISTP
report                   INDC(CPR)-014/LJ (January 1989)            REPPT
report                   Descriptions of UNIFY-ECN & Guide for UsersREPPT

[ top ]

17. CATEGORIES

A. Cross Section and Resonance Integral Calculations

Keywords: angular distribution, elastic scattering, fast neutrons, inelastic scattering, neutron cross sections, spectra.