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NEA-0642 ZZ-UKCTR-1.

ZZ UKCTR-1, Cross-Section Library for Neutron Flux and Neutron Reaction Rates in CTR Calculation

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-UKCTR-1.
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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
ZZ-UKCTR-1 NEA-0642/01 Tested 04-NOV-1981

Machines used:

Package ID Orig. computer Test computer
NEA-0642/01 IBM 3033 IBM 3033
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3. DESCRIPTION OF PROBLEM OR FUNCTION



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  FORMAT: ANISN, DOT, MORSE, SWANLAKE



NUMBER OF GROUPS: 46 energy group structure from 14.2 MeV to 1 MeV  

NUCLIDES: Li-6, Li-7, O, Be, Pb, Nb, Fe, Ni, Cr, Zr, V, Ti, H, D, T, C, Al, B-10, B-11, Cu-63, Cu-65, F, Na, K, Mo.



  ORIGIN: UKNDL



WEIGHTING SPECTRUM: 1/(Sigma t (E).E) weighting is used for groups  1 to 44 with Maxwellian weighting for the two thermal groups.



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UKCTR1 is a data library of neutron cross sections for 25 materials in a 46 energy group structure from 14.2 MeV to 1 MeV. It is designed for calculation of neutron fluxes and reaction rates in controlled thermonuclear reactors. The energy group structure is fine at 14 MeV and there are two thermal groups; the lethargy interval width per energy group for decreasing energy is as follows: 0.014, 0.036, 2 x 0.15, 15 x 0.3, 25 x 0.5, 2.935 and 3.091. Reaction cross sections in- cluding partial inelastic data are provided for the following materials: Li-6, Li-7, O, Be, Pb, Nb, Fe, Ni, Cr, Zr, V, Ti, H, D, T, C, Al, B-10, B-11, Cu-63, Cu-65, F, Na, K, Mo.



1/(Sigma t (E).E) weighting is used for groups 1 to 44 with Max- wellian weighting for the two thermal groups. Anisotropy of scat- tering is represented by a P order up to 4 (usually 0 to 4). Data for hydrogen and deuterium both in water and heavy water and in the  gaseous state is available.



As a supplement, neutron kerma factors are included for each of the  nuclides in the library as well as 98 activation cross sections of importance in fusion reactor work. (These 98 activation cross sections have been extracted from the bulk of the UKCTR-I library to be in a more convenient form for programs such as ANISN.) The kerma factors were computed using the code ENBAL2, a revised ver- sion of ENBAL, which calculates multigroup kerma factors directly from multigroup cross sections together with reaction Q-values. This approach allows neutron heating calculations to be performed consistently with the flux calculation.
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4. METHOD OF SOLUTION

A retrieval program GETEX is supplied with the  library, that extracts data required for a particular calculation in an efficient manner. The cross sections that are thus extracted are in a suitable form for such transport codes as ANISN or MORSE.
A number of modes of output are available in GETEX, the most useful  with ANISN being an "ANISN binary tape" and a "group-independent tape".
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

25 nuclides are in the library in a 46 group structure with a 'P order' up to 4.
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6. TYPICAL RUNNING TIME

For GETEX, dependent on the number of nu- clides to be extracted and the order in which they are given; how- ever extraction very much faster than other retrieval programs.
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7. UNUSUAL FEATURES OF THE PROGRAM

In addition to total cross sec- tions and total scattering matrices, partial cross sections are provided for all neutron-induced reactions of interest, together with partial scattering matrices for each inelastic scattering level and the continuum, (n, 2n) reactions, etc. The library is therefore suitable for sensitivity and error analyses as well as straightforward transport calculations.
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8. RELATED AND AUXILIARY PROGRAMS

The multigroup data in UKCTR-I were prepared using the cross section processing code GALAXY and primary data from UKNDL. A retrieval code GETEX is supplied with the library which produces cross sections that may be used in ANISN, DOT, MORSE, SWANLAKE, etc. The supplementary kerma factors were produced using the code ENBAL2, a development from ENBAL.
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9. STATUS
Package ID Status date Status
NEA-0642/01 04-NOV-1981 Tested at NEADB
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10. REFERENCES

- T.D. Beynon, N.P. Taylor:
  "The UKCTRI Data Library: 46 Group Neutron Cross-Sections for
  Fusion Reactor Calculations"
  University of Birmingham Report No. 79-02 (1979).
- J.A. Price:
  "A Guide to GALAXY 6"
  AWRE O 13/75 (1975).
- A.L. Pope:
"The Current Edition of the Main Tape NDL-1 of the UK Nuclear Data    Library"
  AEEW M1208 (1973).
- (ENBAL) N.P. Taylor:
  "A Study of Neutron Heating in Fusion Reactor Materials"
  Ph.D Thesis, University of Birmingham, Department of Physics
  (1977).
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11. MACHINE REQUIREMENTS

For GETEX - a UKCTRI library tape input unit.  If an ANISN binary tape is required, one output tape unit.
If an ANISN group-independent tape is required, one output tape unit and one scratch unit plus usual card input, line printer output and  card punch output (if required) units.

The card output channel 7 (if required) should have a fixed record length of 80 bytes, the line printer output channel at least 120 bytes.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0642/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

          T. D. Beynon, N. P. Taylor
          University of Birmingham, Department of Physics
          Edgbaston
          Birmingham B15 2TT
          United Kingdom.
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16. MATERIAL AVAILABLE
NEA-0642/01
File name File description Records
NEA0642_01.001 COMPLETE UKCTR-1 DATA SET 35358
NEA0642_01.002 SUPLEMENT UKCTR-1 DATA SET 649
NEA0642_01.003 GETEX PROGRAM SOURCE 472
NEA0642_01.004 SAMPLE PROBLEM INPUT 1 8
NEA0642_01.005 SAMPLE PROBLEM INPUT 2 1
NEA0642_01.006 SAMPLE PROBLEM OUTPUT 1 40
NEA0642_01.007 SAMPLE PROBLEM OUTPUT 2 381
NEA0642_01.008 JCL AND INFORMATION 74
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17. CATEGORIES
  • X. Magnetic Fusion Research
  • Z. Data.

Keywords: anisotropic scattering, cross sections, data, fusion reactors, neutron flux, reaction kinetics, thermonuclear reactions.