1. NAME OR DESIGNATION OF PROGRAM - GRTUNCL 3D 2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE - Program-name Package-ID Orig. Computer Test Computer ------------ ---------- -------------- ------------- GRTUNCL 3D ?????????? Many Computers Sun-EWS, HP-EWS 3. DESCRIPTION OF PROGRAM OR FUNCTION - The existing two-dimensional GRTUNCL code was converted to compute the uncollided fluence at each spatial in an R-theta-Z grid and to generate the associated distributed first-collision source moments for use as a distributed source in the TORT three-dimensional discrete ordinates computed code. Because there is very little information on the GRTUNCL code, reviews of the essential elements underlying the methods were made and the changes performed to convert the exiting code into R-theta-Z version compatible with the TORT distributed source input option. 4. METHOD OF SOLUTION - The representation of the scattering source in discrete ordinates methods stems from the representation of the collisional transfer differential cross section in terms of Legendre expansions. The scattering transfer integral of the equation can be further simplified by using the Legendre Additional Theorem. So the scattering transfer source for a transport problem can be and generally is mathematically represented. This type of representation of the scattering transfer term is standard in most deterministic transport codes although it is generally used in multigroup form with a truncated spherical harmonics expansion of a specified degree. A source in TORT at a spatial mesh in a discrete direction is presented by an expansion of spherical harmonic type with the source moments which the GRTUNCL 3D code needs to calculate. The values of the source moments for the first-collision source are the quantities produced by the extension of GRTUNCL code to 3D for input into TORT. Since the code works only for a point source, the uncollided flux in each spatial mesh is a delta function in direction. As a result, the moments of the flux expansion can be obtained by multiplying the uncollided fluence by the coefficients for the spherical harmonic expansion described above. The first collision source moments are then computed group by group using the group-to-group transfer Legendre expansion coefficients taken from an appropriate multigroup cross section set. This quantity is the desired quantity from running the GRTUNCL code. 5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM - Three-dimensional GRTUNCL 3D is limited in application to appoint source located on Z-axis. 6. TYPICAL RUNNING TIME - 7. UNUSUAL FEATURES OF THE PROGRAM - 8. RELATED AND AUXILIARY PROGRAMS - 9. STATUS - 10. REFERENCES - - F. Masukawa, et al.: GRTUNCL 3D: An Extension of the GRTUNCL Code to Compute R-Theta-Z First Collision Source Moments INS/S99-05(M) Institute of Nuclear Safety Code Manual (March 2000) - F. MASUKAWA, et al.: GRTUNCL-3D: An Extension of the GRTUNCL Code to Compute R-Theta-Z First Collision Source Moments Proc. of ICRS9, J. of NUCL. SCI. & TECHNOL. Suppl. 1, p.471-474 (March 2000) 11. MACHINE REQUIREMENTS - Sun-EWS or HP-EWS 12. PROGRAMMING LANGUAGE USED. - FORTRAN + C 13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED - Sun OS 5.6 or HP-UX9000/785 14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - 15. NAME AND ESTABLISHMENT OF AUTHORS - Contributed by: Institue of Nuclear Safety, NUPEC Tokyo, Japan Developed by: GRTUNCL 3D CRC Research Institue, Inc. Tokyo, Japan 16. CONTENTS OF CODE PACKAGE - Unix compressed tar files containing source files and sample cases. The referenced documentation in postscript files. 17. CATEGORY. G J KEYWORDS - discrete ordinates, neutron, gammma-ray, first-collision source moments, multigroups, two-dimensions, three-dimensions, cylindrical geometry