Computer Programs
NEA-0228 EXCURS-3.
last modified: 01-NOV-1968 | catalog | categories | new | search |

NEA-0228 EXCURS-3.

EXCURS-3, Reactor Kinetics and Heat Transfer in Cylindrical Channel During Accident

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1. NAME OR DESIGNATION OF PROGRAM:  EXCURS-3.
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2. COMPUTERS
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Program name Package id Status Status date
EXCURS-3 NEA-0228/01 Tested 01-NOV-1968

Machines used:

Package ID Orig. computer Test computer
NEA-0228/01 IBM 360 series IBM 360 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

To analize the reactor transient  caused by an accident (insertion of ramp or step reactivity, channel blockage or coast-down of coolant flow), this programme solves completed kinetics and heat equations in a cylindrical channel.
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4. METHOD OF SOLUTION

One point mono-energetic kinetic equation is solved by a modified Runge-Kutta method. Heat equation is solved by  modified Euler method. Temperature dependencies of conductivity density and specific heat of material are expressed by a second order polynomial of temperature. Decay 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 group 1.
   Maximum number of radial mesh points 8.
   Maximum number of axial mesh points 19.
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6. TYPICAL RUNNING TIME

It takes 1 min. / 100 time points in the case  of 8 radial points and 12 axial points.
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7. UNUSUAL FEATURES OF THE PROGRAM

This programme is effective for the problem having strong temperature dependency of heat conduction and  Doppler effect.
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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-0228/01 01-NOV-1968 Tested at NEADB
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10. REFERENCES

REFERENCES.
- S. Saito:
  Kinetics Analysis Code EXCURS (in Japanese)
  JAERI-memo-2515.
- S. Saito:
  Input Description (in English).
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11. MACHINE REQUIREMENTS:  32k.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0228/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  IBM 7044 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-0228/01
File name File description Records
NEA0228_01.001 SOURCE & DATA 360/65 731
NEA0228_01.002 OUTPUT 310
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17. CATEGORIES
  • F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: accidents, kinetics, loss-of-coolant accident, reactor safety, transients.