**1. NAME AND TITLE**

MAP: Kernel Integration Code System in Complex Geometry with Special Application to Surface Sources Determined by Discrete Ordinates Calculations.

Input to MAP may be supplied by CCC-89/DOT-IIW and by GAMLEG, packaged in CCC-42/DTF-IV.

**2. CONTRIBUTOR**

Westinghouse Astronuclear Laboratory, Pittsburgh, Pennsylvania.

**3. CODING LANGUAGE AND COMPUTER**

FORTRAN IV; IBM 360/75/91.

**4. NATURE OF PROBLEM SOLVED**

MAP solves for the last flight radiation transport in an r, z, O geometry. It solves for the nuclear radiation transport to a detector surface from an energy- and angular-dependent surface source defined by the surface leakage data of a DOT-IIW discrete ordinate transport solution in r, z, geometry. During the numerical integration over the surface source, the radiation transport through a three-dimensional geometry described by intersecting quadratic surfaces can be solved. Uncollided energy- and angular-dependent, neutron or photon flux results at a detector plane are provided with the optional use of buildup factor techniques to estimate multiple scattering of photons available. Cross section data for use in the radiation transport can be obtained from 1) internal calculations of point value data from Klein-Nishina relationships and tables for photons, or 2) input values of macroscopic cross sections for materials in zones. General discrete ordinate quadrature data can be used as surface source input with two techniques available to calculate the angular-dependent source data from discrete ordinate data.

**5. METHOD OF SOLUTION**

A variable-interval numerical integration technique is used to integrate the visible surface angular leakage flux at each detector point. Energy dependence is treated as the multigroup data supplied to the code. MAP is applicable to neutron, photon, or coupled neutron-photon analysis; the numerical integration accuracy is dependent upon the input discrete ordinate data.

The code system employs the r,z geometry discrete ordinate transport leakage angular flux data from the DOT-IIW code to calculate neutron and photon transport in a void or in a purely attenuating geometry to provide energy and angular dependent data at a detector surface. The coupling of DOT-IIW calculations through voids is handled by MAP. Photon absorption cross sections may be supplied by a GAMLEG-W library tape. Discrete ordinate transport angular leakage flux data are supplied by the DOT-IIW code system as the scalar flux output tape.

**6. RESTRICTIONS OR LIMITATIONS**

MAP uses complete, flexible dimensioning to facilitate dynamic core storage allocation at execution time and during various phases of the calculation. Because of the use of a flexible dimensioning technique for each array, during a specific phase of the calculation, no size restriction is imposed for a given array. The only restriction is the size of the sum of all array storage required during a specific phase of the calculation. The required storage size for a given problem may be exactly computed as indicated in the documentation. The size of BLANK COMMON must be compiled with a fixed dimension in the main subroutine.

**7. TYPICAL RUNNING TIME**

Estimated running time of the sample problem on the IBM 360/91: 6.5 seconds.

**8. COMPUTER HARDWARE REQUIREMENTS**

MAP is operable on the IBM 360. The source program requires 22K decimal locations; the remaining locations are used for problem data storage. Up to six tape or disk devices are required in addition to input, output, and punch disks.

**9. COMPUTER SOFTWARE REQUIREMENTS**

The packaged version of MAP is written in standard USASI FORTRAN IV. With minor change the code can be used on the CDC 6600 or UNIVAC 1108 computers. It is operational under the IBM 360/75 Release 18 Monitor System.

**10. REFERENCES**

a. Included in package:

R. K. Disney, R. G. Soltesz, J. Jedruch, and S. L. Zeigler, *Code Description and
User's Manual for the MAP Radiation Transport Computer Code*, WANL-TME-2706
(August 1970).

b. Background information:

R. G. Soltesz, R. K. Disney, and G. Collier, *User's Manual for the DOT-IIW
Discrete Ordinates Transport Computer Code*, WANL-TME-1982 (December 1969).

F. R. Mynatt, F. J. Muckenthaler, and P. N. Stevens, *Development of Two-
Dimensional Discrete Ordinates Transport Theory for Radiation Shielding*, CTC-
INF-952 (August 1969).

R. G. Soltesz, R. K. Disney, and S. L. Zeigler, *Cross Section Generation and Data
Processing Techniques*, WANL-PR(LL)-034, Volume 3 (August 1970).

**11. CONTENTS OF CODE PACKAGE**

Included are the referenced document (a) and a reel of magnetic tape which contains the source code and sample problem input written in BCD/EBCDIC card images, plus output from the sample problem written in list format; total records 3877.

**12. DATE OF ABSTRACT**

February 1972; revised December 1984.

**KEYWORDS: ** KERNEL; COMPLEX GEOMETRY; NEUTRON; GAMMA-
RAY; DISCRETE ORDINATES