CCC-0431 MORSE-C.

MORSE-C, Neutron Transport, Gamma Transport for Criticality Calculation by Monte-Carlo Method

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-C.

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.

Program name	Package id	Status	Status date
MORSE-C	CCC-0431/01	Arrived	08-FEB-2002

Machines used:

Package ID	Orig. computer	Test computer
CCC-0431/01	CDC 7600

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3. DESCRIPTION OF PROGRAM OR FUNCTION

MORSE-C is a Monte-Carlo code to solve the multiple energy group form of the Boltzmann transport equation in order to obtain the eigenvalue (multiplication) when fissionable materials are present. Cross sections for up to 100 energy groups may be employed. The angular scattering is treated by the usual Legendre expansion as used in the discrete ordinates codes. Upscattering may be specified. The geometry is defined by relationships to general 1st or 2nd degree surfaces. Array units may be spcified. Output includes, besides the usual values of input quantities, plots of the geometry, calculated volumes and masses, and graphs of results to assist the user in determining the correctness of the problem's solution.

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4. METHOD OF SOLUTION:

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

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6. TYPICAL RUNNING TIME:

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7. UNUSUAL FEATURES OF THE PROGRAM

The code has been specially designed to solve neutron criticality problems.

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8. RELATED AND AUXILIARY PROGRAMS:

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9. STATUS

Package ID	Status date	Status
CCC-0431/01	08-FEB-2002	Masterfiled Arrived

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10. REFERENCES:

CCC-0431/01, included references:

- E.A. Straker, P.N. Stevens, D.C. Irving, and V. R. Cain:
  The MORSE Code - A Multigroup Neutron and Gamma-Ray Monte Carlo
  Transport Code
  ORNL-4585 (September 1970).
- M.B. Emmett:
  The MORSE Monte Carlo Radiation Transport Code System
  ORNL-4972/R1 (February 1983)
- T.P. Wilcox:
  MORSE-C, A CDC-7600 Program Designed to Solve Nuclear Criticality
  Problems by Using the Monte Carlo Neutron Method
  Informal Report UCID-18993 (January 1981)

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11. MACHINE REQUIREMENTS:

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
CCC-0431/01	FORTRAN-IV

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.
Developed by:   Lawrence Livermore National Laboratory, Livermore, CA, USA

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16. MATERIAL AVAILABLE

CCC-0431/01

source program   mag tapeSource Program (CHAT FORTRAN)              SRCTP
test-case data   mag tapeSample Problem Input                       DATTP
test-case output mag tapeSample Problem Output                      OUTTP
bin data lib     mag tapeN92GRP Library from LLNL ENDL Cmp.(11/1976)LBBTP
report                   ORNL-4972/R1  (February 1983)              REPPT
report                   UCID-18993  (January 1981)                 REPPT
report                   ORNL-4585 (September 1970)                 REPPT

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17. CATEGORIES

C. Static Design Studies
J. Gamma Heating and Shield Design

Keywords: Monte Carlo method, anisotropic scattering, criticality, cross sections, gamma radiation, multigroup, neutrons, one-dimensional, shielding, three-dimensional, time dependence, transport theory, two-dimensional.