Computer Programs
DLC-0028 ZZ-CTR.
last modified: 01-OCT-1975 | catalog | categories | new | search |

DLC-0028 ZZ-CTR.

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

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1. NAME

ZZ-CTR.

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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
ZZ-CTR DLC-0028/01 Tested 01-OCT-1975

Machines used:

Package ID Orig. computer Test computer
DLC-0028/01 IBM 370 series IBM 370 series
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3. DESCRIPTION

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
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 6Li, 7Li, Nb, C, Fe, Cu, Li, 203Al, 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 CTR library can be used for neutron and secondary gamma-ray transport or for primary gamma-ray transport in fusion reactor neutronics studies.

CTR is a coupled set of cross sections for materials typically considered for use in some conceptual fusion reactor neutronics studies.

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4. METHODS

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.

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6. TYPICAL RUNNING TIME

Using the retrieval program to convert to an unformatted tape requires 45 seconds on the IBM 360/91.

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8. RELATED OR 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.

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9. STATUS
Package ID Status date Status
DLC-0028/01 01-OCT-1975 Tested at NEADB
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10. REFERENCES
DLC-0028/01, included references:
- J.T. Kriese: 'Coupled Neutron and Gamma-Ray Cross Section Sets for Fusion
Reactor Calculations', ORNL-TM-4277 (1973).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
DLC-0028/01 FORTRAN-IV
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14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The latest version DLC-28B, dated May 1974, has a data set for fluorine added.

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15. NAME AND ESTABLISHMENT OF AUTHORS

Reactor Division

Oak Ridge National Laboratory

Oak Ridge, TN

USA

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16. MATERIAL AVAILABLE
DLC-0028/01
File name File description Records
DLC0028_01.001 DATA LIBRARY (BCD) 14521
DLC0028_01.002 RETRIEVAL PROGRAM (F4) 140
DLC0028_01.003 JCL + DATA FOR SAMPLE PROBLEM 8
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17. CATEGORIES
  • Z. Data

Keywords: ENDF/B, cross sections, data, fusion reactions, gamma radiation, multigroup, neutrons, transport theory.