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NEA-1181 MORSE-DD.

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

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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


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  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:

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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.