NEA-1540 SCRELA.

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

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, SOLUTION, RESTRICTIONS, TYPICAL RUNNING TIME, FEATURES, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: SCRELA.

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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
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.