DLC-0011 Z-DLC-11/RITTS.

1. NAME OR DESIGNATION OF PROGRAM:  ZZ-DLC-11/RITTS.  121 group coupled neutron and gamma-ray cross section data for transport codes.

3. NATURE OF PHYSICAL PROBLEM SOLVED

  FORMAT: ANISN, DTF-4, DOT and MORSE.

NUMBER OF GROUPS: 100 neutron energy groups (14.92 MeV to thermal)                      21 gamma-ray energy groups (14.0 to 0.01 MeV)

NUCLIDES: H, C, O, N, Na, Mg, P, S, Cl, K, and Ca, (microscopic cross sections) and 9 organic materials including 11-element standard man, 4-element standard man, skin, bone, tissue, brain, lung, red marrow, and muscle (macroscopic cross sections).

  ORIGIN: ENDF/B for H, C, N, O, Na, and Mg
          O5R library for Ca, S, and K
          GAM-2 library for Cl
          Evaluation by J. J. Ritts for P.

WEIGHTING SPECTRUM: 1/E for the top 99 groups and Maxwellian for the thermal group values.

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DLC-11 data is suitable for neutron, gamma-ray, or coupled neutron and gamma-ray transport calculations. It is intended for use in multigroup discrete ordinates or Monte Carlo transport codes  which treat anisotropic scattering by Legendre expansion up to order P3.
DLC-11 is a collection of multigroup cross section data which were compiled by J. J. Ritts for use in depth-dose calculations in anthropomorphic phantoms. For convenience the data are grouped as follows

1. A coupled 121-group (100 neutron, 21 gamma-ray) set of data for  the 11 elements H, C, O, N. Na, Mg, P, S, Cl, K, and Ca. This  set includes P3 coupled 121-group microscopic cross sections     plus 121-group kerma factors for the 11 elements.
2.  A 100-group set of neutron cross sections for the 11 elements.
3. A coupled 121-group set of macroscopic cross sections for 9  organic materials including 11-element standard man, 4-element  standard man, skin, bone, tissue, brain, lung, red marrow, and     muscle.

4. METHOD OF SOLUTION

The basic data sources were ENDF/B for H, C, N, O, Na, and Mg, the O5R library for Ca, S, and K, the GAM-2 library for Cl and an evaluation by Ritts for P. A 1/E spectrum was assumed for averaging the top 99 groups and a Maxwellian for averaging the thermal group values.
The gamma-ray cross sections were computed from DLC-3/HPIC using MUG.
The neutron-to-gamma-ray group transfer cross sections were generated, using POPOP-4, with account being taken for neutron capture, inelastic scattering, and other neutron reactions.
The 100-group neutron kerma factors were generated by DLC-10/ AVKER and the 21-group gamma-ray kerma factors by MUG.
The DLC-11 cross sections represent a P3 approximation to elastic (or Compton) scattering angular distributions. The 100 neutron groups cover an energy range from 14.92 MeV to thermal. For  gamma-rays, 21 energy groups cover the range from 14.0 to 0.01 MeV. The group structures are given in ref. 2.

6. TYPICAL RUNNING TIME

The sample problem runs approximately 45 seconds CPU time, 230 seconds total time on IBM 360/91. The problem involves reading the 100 group neutron data for C, Na, and K, multiplying all data by 1.0, and writing the results on an unformatted tape.

7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM

8. RELATED AND AUXILIARY PROGRAMS

The retrieval program JRMACRO is used to read microscopic, multigroup, PN expansion cross section data, 'mix' this data into macroscopic cross section data as needed, and write the resulting set in a suitable output format. The cross section data considered here is of the general type used by particle transport computer codes such as DTF-4, ANISN, DOT, and MORSE.
JRMACRO accepts input cross sections by means of cards, tape written in card image format, an unformatted tape (binary), or a combination of the above. Formatted input (card or card image tape)  is first read and stored on a tape or disk before any mixing of cross section data is performed.
The output cross section data may be in the form of a card image tape, an unformatted tape, or both.

-R.J. Ritts, R.W. Roussin, I.J.Brown;
"JRMACRO: A Program for Converting Microscopic, Multigroup, P,
Expansion Cross Section Data into Corresponding
Macroscopic Data for Mixtures or Compounds"
ORNL-TM-3052
- J.J. Ritts, R.W. Roussin ;
"121 Group Coupled Neutron and Gamma-Ray
Cross-Section Library for Transport Codes (100 Neutron,
21 Gamma-Ray Groups)" Informal notes.
- R.W. Roussin ;
"Using ANISN to Reduce the DLC-2 100 Group
Cross-Section Data to a  Smaller Number of Groups"
ORNL-TM-3049
- J.J. Ritts, M.Solomito, P.N.Stevens;
"The calculation of Neutron-Induced Physical Doses
in Human Tissues"  (ORNL-TM-2991)

11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS

13. SOFTWARE REQUIREMENTS: OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS. The
current version of DLC-11 is dated April 1970.

15. NAME AND ESTABLISHMENT OF AUTHOR

Westinghouse Electric Corporation
Advanced Reactors Division
Waltz Mill Site
Madison, PA. 15663, U. S. A.

and

Computing Technology Center
Union Carbide Corporation, Nuclear
Division, Oak Ridge, Tennessee.

File name	File description	Records
DLC0011_01.001	INFORMATION	11
DLC0011_01.002	X-SEC LIBRARY FILE 1	36475
DLC0011_01.003	X-SEC LIBRARY FILE 2	13522
DLC0011_01.004	X-SEC LIBRARY FILE 3	8445
DLC0011_01.005	JRMACRO ASSEMBLER ROUTINE (SOURCE)	39
DLC0011_01.006	JRMACRO SOURCE PROGRAM	328
DLC0011_01.007	JRMACRO SAMPLE PROBLEM DD-CARDS AND DATA	21
DLC0011_01.008	JRMACRO SAMPLE PROBLEM PUNCHED OUTPUT	1469
DLC0011_01.009	JRMACRO SAMPLE PROBLEM OUTPUT	921