NEA-0424 EXCURS.

EXCURS, Heat Transfer Transients in Cylindrical Reactor Channel LOCA

NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, 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 OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: EXCURS.

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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
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.