NEA-1181 MORSE-DD.

MORSE-DD, Monte-Carlo Neutron Transport with Combinatorial Geometry Using DDL Cross-Sections Library

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: MORSE-DD.

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2. COMPUTERS

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Program name	Package id	Status	Status date
MORSE-DD	NEA-1181/01	Arrived	07-DEC-2001
ZZ-DDXLIB1	NEA-1181/02	Arrived	31-MAY-2001

Machines used:

Package ID	Orig. computer	Test computer
NEA-1181/01	FACOM M-380

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3. DESCRIPTION OF PROGRAM OR FUNCTION

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%

  FORMAT: MORSE

  NUMBER OF GROUPS: 125 groups

NUCLIDES: H, Li, C, Be, N, O, Na, Mg, Al, Si, K, Ca, Cr, Fe, Ni, Mn, Cu, Mo, Pb.

  ORIGIN: ENDF/B-IV, JENDL3-PR1

  WEIGHTING SPECTRUM:

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%

Neutron transport calculation in arbitrary geometry. This is a revised version of MORSE-CG developed by ORNL. Multi-group double differential form cross sections are used as a library in addition to a Pl library.

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4. METHOD OF SOLUTION

Monte Carlo method. The code can continuously sample a scattering angle mu.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Number of energy groups for DDL/B4 library: 125 groups. Geometry input: combinatorial geometry.

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6. TYPICAL RUNNING TIME

Depends on problem and required precision. CPU is comparable with original MORSE-CG.

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7. UNUSUAL FEATURES OF THE PROGRAM

The program is effective in solving accurately transport equations in mediums with highly anisotropic scattering cross sections such as a fusion reactor.

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8. RELATED AND AUXILIARY PROGRAMS: PROF-DD to make DDL type cross section.

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9. STATUS

Package ID	Status date	Status
NEA-1181/01	07-DEC-2001	Masterfiled Arrived
NEA-1181/02	31-MAY-2001	Masterfiled Arrived

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10. REFERENCES:

NEA-1181/01, included references:

- M. Nakagawa and T. Mori:
  MORSE-DD - A Monte Carlo Code Using Multi-Group Double
  Differential Form Cross Sections.
  JAERI-M-84-126  (July 1984)

NEA-1181/02, included references:

- M. Nakagawa and T. Mori:
  MORSE-DD - A Monte Carlo Code Using Multi-Group Double
  Differential Form Cross Sections.
  JAERI-M-84-126  (July 1984)

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11. MACHINE REQUIREMENTS: Variable dimension. Clock is necessary.

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
NEA-1181/01	FORTRAN+ASSEMBLER

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED: FACOM OSIV/F4.

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS: No.

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15. NAME AND ESTABLISHMENT OF AUTHORS

          M. Nakagawa and T. Mori
          Department of Reactor Engineering
          Japan Atomic Energy Research Institute
          Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan

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16. MATERIAL AVAILABLE

NEA-1181/01

source program   mag tapeSource Program (Fortran)                   SRCTP
source program   mag tapeSource Program (Assembler)                 SRCTP
test-case data   mag tapeJCL to Compile                             DATTP
test-case data   mag tapeJCL for Execution                          DATTP
test-case data   mag tapeSAmple Input Data                          DATTP
test-case output mag tapeSample Output                              OUTTP
symb data lib    mag tapeDouble Differential Form X-sec lib         LBSTP
report                   JAERI-M-84-126  (July 1984)                REPPT

NEA-1181/02

symb data lib mag tapeDDX Code Library LBSTP
report JAERI-M-84-126 (July 1984) REPPT

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17. CATEGORIES

C. Static Design Studies
J. Gamma Heating and Shield Design
X. Magnetic Fusion Research

Keywords: Monte Carlo method, anisotropic scattering, criticality, cross sections, fusion reactors, neutron transport theory, shielding, three-dimensional.