**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:

^{6}Li, ^{7}Li, O, Be, Pb, Nb, Fe, Ni, Cr, Zr, V, Ti, H, D, T, C, Al, ^{10}B, ^{11}B, ^{63}Cu, ^{65}Cu, 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.

**KEYWORDS: ** ANISN FORMAT; CTR NEUTRONICS CROSS SECTIONS; KERMA
FACTORS; MULTIGROUP CROSS SECTIONS; MULTIGROUP CROSS
SECTIONS BASED ON ENDF/B; NEUTRON CROSS SECTIONS; REACTION
CROSS SECTIONS