1. NAME AND TITLE OF DATA LIBRARY

UKCTRI-81: 46-Group Neutron Cross Sections and Kerma Factors for Fusion Reactor Calculations.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

GETEX: Converts the data to ANISN format.

3. CONTRIBUTOR

University of Birmingham, Birmingham, England.

4. HISTORICAL BACKGROUND AND INFORMATION

In the analysis of the neutronics of proposed designs for controlled thermonuclear reactor (CTR) blankets, a common technique for the computation of neutron fluxes and reaction rates is the use of a multigroup transport code such as ANISN or MORSE. The data used in such calculations are often drawn from a library of cross sections produced primarily for fission reactor calculations or, at best, using one of the standard energy group structures derived for fission work. The need for a library of multigroup cross sections suitable for CTR calculations has given rise to the development of the UKCTRI data library.

5. APPLICATION OF THE DATA

The UKCTRI data set is a library of 46-group neutron cross sections for 25 nuclides or materials, intended to be used with neutron transport codes such as ANISN or MORSE for the computation of neutron fluxes and reaction rates in fusion reactor blanket configurations and integral experiments related to CTR analysis.

6. SOURCE AND SCOPE OF DATA

Cross sections for 25 materials commonly used in fusion reactor calculations are provided in an energy group structure of 46 groups which feature narrow groups in the higher energy region where a number of important threshold reactions occur and broader groups at the lower energies. In addition to total cross sections 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, (n,2n) reactions, etc. The retrieval program GETEX is used to extract required data from the library and present to ANISN as an "ANISN binary library tape" or as a "group-independent tape."

Neutron heating (kerma) factors have been computed for all 25 nuclides in the UKCTR-I data library and can be used with that library and a standard neutron transport code for the computation of neutron heating rates in fusion reactor design calculations. The factors are accompanied by activation cross sections for 98 reactions used in fusion reactor work.

The nuclides for which data are included are:

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

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

GETEX, which is part of the package, can be used to retrieve the data sets.

8. DATA FORMAT AND COMPUTER

IBM 370.

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCES

T. D. Beynon and N. P. Taylor, "The UKCTRI Data Library: 46-Group Neutron Cross Sections for Fusion Reactor Calculations," Paper No. 79-02.

N. P. Taylor, "46-Group Neutron Heating Factors for the UKCTR-I Data Library," Paper No. 80-01.

11. CONTENTS OF LIBRARY

Included are the referenced documents and one (1.2MB) DOS diskette which contains the cross sections, kerma factors, and GETEX retrieval program and input for the GETEX sample problem, plus output from the sample problem.

12. DATE OF ABSTRACT

March 1985.