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NEA-1540 SCRELA.

SCRELA, LOCA Analysis of Super-Critical Light-Water Reactors

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1. NAME OR DESIGNATION OF PROGRAM:  SCRELA.
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2. COMPUTERS
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Program name Package id Status Status date
SCRELA NEA-1540/02 Tested 11-AUG-2001

Machines used:

Package ID Orig. computer Test computer
NEA-1540/02 UNIX W.S. PC Pentium III,Linux-based PC
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3. DESCRIPTION OF PROGRAM OR FUNCTION

LOCA Analysis Code for the Supercritical-Water Cooled Reactor.
- Blowdown Module: Calculation of the Blowdown Phase and Refill Phase.
- Reflood Module: Calculation of the Reflood Phase.
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4. METHODS: METHOD OF SOLUTION
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME: Blowdown Module: 3-4 hours. Reflood Module: About 5 days.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED AND AUXILIARY PROGRAMS:  FORTRAN 77 version. Steam Table Library.
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9. STATUS
Package ID Status date Status
NEA-1540/02 11-AUG-2001 Tested at NEADB
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10. REFERENCES

- J.H. Lee, S. Koshizuka and Y. Oka:
Development of a LOCA Analysis Code for the Supercritical-Pressure    Light Water Reactors,
  Submitted to Nuclear Technology (February 1996)
NEA-1540/02, included references:
- Jong Ho Lee, Seiichi Koshizuka and Yoshiaki Oka:
  Manual of SCRELA Code
  SCRELA: Supercritical-Water Cooled Reactor LOCA Analysis Code
  (September 1996)
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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1540/02 FORTRAN-77
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13. SOFTWARE REQUIREMENTS: 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

       J.H. Lee, S. Koshizuka and Y. Oka
       Nuclear Eng. Research Lab.
       Faculty of Eng.
       University of Tokyo
       Japan
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16. MATERIAL AVAILABLE
NEA-1540/02
/source Source code used in "blowdown" and "reflood" modules
/bout Output files from the execution of "blowdown"
/rout Output files from the execution of "reflood"
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: blowdown, loss-of-coolant accident, reflooding, water cooled reactors.