1. NAME AND TYTLE                                                              
      SCRELA:  Supercritical-Water Cooled Reactor LOCA Analysis Code            
                                                                                
 2. CONPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION            
    PACKAGE AVAILABLE                                                           
   - SUN Workstation                                                            
                                                                                
 3. DESCRIPTION OF PROGRAM                                                      
     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.                       
                                                                                
 4. METHOD OF SOLUTION                                                          
                                                                                
 5. RESTRICTIONS ON THE COMPLEXITY OF THE PROGRAM                               
                                                                                
 6. TYPICAL RUNNING TIME                                                        
     - Blow down Module: 3~4 hours                                              
     - Reflood Module:   about 5 days                                           
                                                                                
 7. UNUSUAL FEATURES OF THE PROGRAM                                             
                                                                                
 8. RELATED AND AUXILIARY PROGRAMS                                              
   - FORTRAN 77 version                                                         
   - Steam Table Library                                                        
                                                                                
 9. STATUS                                                                      
   - 1996.9.14                                                                  
                                                                                
10. REFERENCES                                                                  
   - J.H.Lee, S.Koshizuka, and Y.Oka, Feb.1996 "Development of LOCA             
  Analysis Code for the Supercritical-Pressure, Light Water Reactors",          
  submitted to Nuclear Technology.                                              
   - J.H.Lee,S.Koshizuka, and Y.Oka, Sept.1996 "Manual of SCRELA Code,          
  SCRELA: Supercritical-Water Cooled Reactor LOCA Analysis Code",               
  Nuclear Eng. Research Lab., Faculty of Eng., University of Tokyo,             
  Japan.                                                                        
                                                                                
11. MACHINE REQUIREMENTS                                                        
                                                                                
12. PROGRAMMING LANGUAGE USED                                                   
   - FORTRAN 77                                                                 
                                                                                
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED                            
                                                                                
14. OTHER PROGRAMMMING OPERATING INFORMATION ON RESTRICTION                     
                                                                                
15. NAME AND ESTABLISHMENT OF AUTHORS                                           
   - Developed by; J. H. Lee,  S. Koshizuka,  and Y. Oka                        
                   Nuclear Eng. Research Lab.,                                  
                   Faculty of Eng., University of Tokyo, Japan                  
                                                                                
16. MATERIAL AVAILABLE                                                          
                                                                                
17. CATEGORIES                                                                  
                                                                                
    KEYWORDS: LOCA CODE; SUPERCRITICAL-WATER COOLED REACTOR