last modified: 07-JUL-1989 | catalog | categories | new | search |

NEA-0537 SCOTCH.

SCOTCH, 1-D 2 Group HTGR Core Kinetics with Temperature Transients and Fluid Dynamic

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1. NAME OR DESIGNATION OF PROGRAM:  SCOTCH.
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2. COMPUTERS
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Program name Package id Status Status date
SCOTCH NEA-0537/01 Tested 07-JUL-1989

Machines used:

Package ID Orig. computer Test computer
NEA-0537/01 FACOM 230/75 DEC VAX 8810
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3. NATURE OF PHYSICAL PROBLEM SOLVED

This programme solves the one-dimensional (r or z), two-group reactor kinetics equations with multi-channel temperature transients and fluid dynamics for a HTGR core.
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4. METHOD OF SOLUTION

The finite difference equation of one-dimensional neutron diffusion is solved by a direct method and the finite difference equations of heat conduction and fluid dynamics are solved by the Peaceman-Rachford method.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The core storage required is 102k words. The max number of meshpoints for the diffusion equation is 99 and the limit for regions with constant properties is 10.
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6. TYPICAL RUNNING TIME

The running time is about 25 minutes for the case with 20 neutron meshpoints for the diffusion equation and 3 channels for heat conduction and  fluid dynamics.
NEA-0537/01
NEA-DB ran the test cases included in this package on a VAX 8810 computer. Execution times were between 8 and 32 seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM

This programme is suitable for analysis of control rod ejection accidents with rapid depressurization in the cooling loop of a HTGR plant and analysis of stability of power and flow dynamics interaction in a gas cooled reactor.
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8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
NEA-0537/01 07-JUL-1989 Tested at NEADB
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10. REFERENCES
NEA-0537/01, included references:
M. Ezaki, T. Ozawa and S. Mitake:
'SCOTCH' - A Program for the Solution of the One-Dimensional, Two
Group, Space-Time Neutron  Diffusion Equations with Temperature
Feedback of Multi-Channel Fluid Dynamics for HTGR Cores
JAERI-M 8292 (1979) (in Japanese).
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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0537/01 FORTRAN-IV
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13. SOFTWARE REQUIREMENTS: OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED
NEA-0537/01
VAX/VMS V5.01.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

    Masahiro Ezaki and Tamotsu Ozawa
    Division of Power Reactor Projects,
    Japan Atomic Energy Research Institute
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16. MATERIAL AVAILABLE
NEA-0537/01
File name File description Records
NEA0537_01.001 INFORMATION FILE 89
NEA0537_01.002 FORTRAN SOURCE PROGRAM 7388
NEA0537_01.003 VAX COMMAND PROCEDURE 5
NEA0537_01.004 TEST CASE 1 INPUT 470
NEA0537_01.005 TEST CASE 2 INPUT 470
NEA0537_01.006 TEST CASE 3 INPUT 470
NEA0537_01.007 TEST CASE 1 OUTPUT ON FACOM 763
NEA0537_01.008 TEST CASE 3 OUTPUT ON VAX 614
NEA0537_01.009 TEST CASE 2 OUTPUT ON VAX 618
NEA0537_01.010 TEST CASE 3 OUTPUT ON VAX 1090
NEA0537_01.011 TEST CASE 1 PUNCHED OUTPUT (VAX) 259
NEA0537_01.012 TEST CASE 2 PUNCHED OUTPUT (VAX) 259
NEA0537_01.013 TEST CASE 3 PUNCHED OUTPUT (VAX) 197
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17. CATEGORIES
  • F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
  • H. Heat Transfer and Fluid Flow

Keywords: HTGR reactors, feedback, fluid flow, heat transfer, neutron diffusion equation, one-dimensional, reactor kinetics, space-time, transients, two-group.