last modified: 20-FEB-1981 | catalog | categories | new | search |

NEA-0424 EXCURS.

EXCURS, Heat Transfer Transients in Cylindrical Reactor Channel LOCA

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1. NAME OR DESIGNATION OF PROGRAM:  EXCURS.
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2. COMPUTERS
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Program name Package id Status Status date
EXCURS NEA-0424/01 Tested 20-FEB-1981

Machines used:

Package ID Orig. computer Test computer
NEA-0424/01 CDC 7600 CDC 7600
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3. NATURE OF PHYSICAL PROBLEM SOLVED

To analyze the reactor dynamics and transient caused by an accident (insertion of ramp or step reactivity, channel blockage or coolant flow coast-down). This program solves complete kinetics and heat transfer equations in a cylindrical channel. It consists of three channels, average, hot and hottest (with engineering hot channel factor).
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4. METHOD OF SOLUTION

One-point mono-energetic equation is solved by a modified Runge-Kutta-Gill method. Temperature dependence of physical properties of material are expressed by a second order polynomial of temperature. Decay heat after reactor shut down is also taken into account. A technique for self-adjusting the time interval is available.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Number of energy groups - 1
maximum number of radial mesh points in fuel region - 13
maximum number of axial mesh points - 19
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6. TYPICAL RUNNING TIME

Two minutes per 1000 time steps in the case of 10 radial points and 12 axial points for 2 channels.
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7. UNUSUAL FEATURES OF THE PROGRAM

This program is effective for the accident analysis of LMFBR introducing scram action.
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8. RELATED AND AUXILIARY PROGRAMS:  EXPLOT - to plot the calculated results.
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9. STATUS
Package ID Status date Status
NEA-0424/01 20-FEB-1981 Tested at NEADB
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10. REFERENCES

- S. Saito:
  'Kinetics Analysis Code EXCURS' (in Japanese)
  JAERI-Memo 2515.
NEA-0424/01, included references:
- S. Saito:
  'EXCURS, A Computing Programme for the Analysis of Reactor Core
   Transients'
   RCN-73-073 (July 1973).
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11. MACHINE REQUIREMENTS:  64k of core storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0424/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  CDC6600 FORTRAN monitor.
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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

    S. Saito
    Tokai Research Establishment
    JAERI
    Tokai-Mura, Naka-Gun, Ibaraki-Ken
    Japan.
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16. MATERIAL AVAILABLE
NEA-0424/01
File name File description Records
NEA0424_01.002 INFORMATION FILE 11
NEA0424_01.003 SOURCE FORTRAN 1546
NEA0424_01.004 S.P. INPUT 30
NEA0424_01.005 S.P. OUTPUT 3567
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17. CATEGORIES
  • F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: LMFBR reactors, heat transfer, loss-of-coolant accident, radiation heat, reactor channels, reactor kinetics, reactor safety, transients.