DLC-0028: ZZ DLC-28, 73-Group Neutron and Gamma Coupled Cross-Section for CTR Transport Calculation

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DLC-0028 ZZ-DLC-28. (Abstract last modified 01-OCT-1975)

ZZ DLC-28, 73-Group Neutron and Gamma Coupled Cross-Section for CTR Transport Calculation

Abstract Table of Contents:

1. NAME OR DESIGNATION OF PROGRAM - ZZ-DLC-28. 73-group P3 coupled neutron and gamma-ray cross sections for fusion reactor calculations.

2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name Package-ID Status ZZ-DLC-28 DLC-0028/01 Tested

Machines used: Package-ID Orig.Computer Test Computer DLC-0028/01 IBM 370 series IBM 370 series

3. NATURE OF PHYSICAL PROBLEM SOLVED -
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FORMAT: ANISN, DOT, or MORSE.
NUMBER OF GROUPS: 52 neutron groups plus 21 gamma-ray groups.
NUCLIDES: materials typically considered for use in some conceptual fusion reactor neutronics studies.These materials include Li-6, Li-7, Nb, C, Fe, Cu, Li, Al-203, Mg, H, O, Pb, Ta, V, and B.
ORIGIN: ENDF/B or DNA data sets; for lead and boron, the GAM-2 library at ORNL.
WEIGHTING SPECTRUM: The data were collapsed from a fine-group structure using a weighting function typical of the average spectrum in a fusion reactor blanket.
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The DLC-28 library can be used for neutron and secondary gamma-ray transport or for primary gamma-ray transport in fusion reactor neutronics studies.
DLC-28/CTR is a coupled set of cross sections for materials typically considered for use in some conceptual fusion reactor neutronics studies. These materials include 6-Li, 7-Li, Nb, C, Fe, Cu, Li, Al-203, Mg, H, O, Pb, Ta, V, and B.

4. METHOD OF SOLUTION -
The data were collapsed from a fine-group structure using a weighting function typical of the average spectrum in a fusion reactor blanket.
With the exception of lead and boron, 100 energy-group neutron cross sections were obtained from ENDF/B or DNA data sets using SUPERTOG. A flux weighting function of 1/E was used in SUPERTOG and all resonance nuclides were treated as infinitely dilute. The energy group structure coincided with the GAM-2 group structure for the top 99 groups, and the 100th group was a thermal group (Maxwellian distribution was assumed).
For lead and boron, the GAM-2 library at ORNL was employed to obtain the 100-group neutron cross sections.
SMUG, an updated version of MUG, was used to calculate 21 energy-group gamma-ray transport cross sections for all nuclides except lead and boron. The gamma-ray transport cross sections for lead and boron are from MUG.
Secondary gamma-ray production cross sections for 100 neutron groups and 21 gamma-ray groups were obtained from several data bases.
A coupled 100 neutron energy-group and 21 gamma-ray energy- group cross section set was formed and then collapsed to 52 neutron groups plus 21 gamma-ray groups using the group collapsing feature of the ANISN code. The spectrum used for the collapsing was, therefore, a spatial average of the energy distribution in a fusion reactor blanket.
The energy-group structures used are given in ref. 1. a P3 Legendre expansion was used to represent neutron elastic scattering and photon Compton scattering.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM -

6. TYPICAL RUNNING TIME - Using the retrieval program to convert to an unformatted tape requires 45 seconds on the IBM 360/91.

7. UNUSUAL FEATURES OF THE PROGRAM -

8. RELATED AND AUXILIARY PROGRAMS - LIBGEN - is a modified version of the library generation routine available in the ANISN code package. This version reads the card image CTR tape and converts it into an unformatted library tape for direct use in ANISN, DOT, or MORSE.

9. STATUS
DLC-0028/01: 01-OCT-1975 Tested at NEADB

10. REFERENCES -
- J.T. Kriese:
'Coupled Neutron and Gamma-Ray Cross Section Sets for Fusion Reactor Calculations'
ORNL-TM-4277 (1973).
DLC-0028/01:

11. MACHINE REQUIREMENTS -

12. PROGRAMMING LANGUAGE(S) USED -
DLC-0028/01: FORTRAN-IV

13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED -

14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - The latest version DLC-28B, dated May 1974, has a data set for fluorine added.

15. NAME AND ESTABLISHMENT OF AUTHOR -
Reactor Division
Oak Ridge National Laboratory

16. MATERIAL AVAILABLE -
DLC-0028/01:
DLC0028_01.001    DATA LIBRARY (BCD)                              14521 records
DLC0028_01.002    RETRIEVAL PROGRAM (F4)                            140 records
DLC0028_01.003    JCL + DATA FOR SAMPLE PROBLEM                       8 records

17. CATEGORIES  -

- X.  Magnetic Fusion Research
- Z.  Data.

Keywords: CROSS SECTIONS, DATA, ENDF/B, FUSION REACTIONS, GAMMA RADIATION, MULTIGROUP, NEUTRONS, TRANSPORT THEORY