88-Ra-224 TIT        EVAL-AUG88 N.TAKAGI                         
                      DIST-DEC21                       20130308   
----JENDL-5           MATERIAL 8828                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
21-11 revised by O.Iwamoto                                        
      (MF8/MT4,16,17,37,102) added                                
                                                                  
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              The data were taken from JENDL-3.3.                 
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   JENDL-3.2 data were automatically transformed to JENDL-3.3.    
    Interpolation of spectra: 22 (unit base interpolation)        
    (3,251) deleted, T-matrix of (4,2) deleted, and others.       
   ===========================================================    
                                                                  
HISTORY                                                           
88-08 NEW EVALUATION WAS MADE BY N. TAKAGI (TOKYO INSTITUTE OF    
      TECHNOLOGY, TIT)                                            
13-03 The data for mf/mt=5/16,17,37 were converted to tabular     
      forms in order to avoid negative Kerma factors.             
      The modification was done by K.Shibata (jaea).              
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451   COMMENT AND DICTIONARY                                 
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151   RESONANCE PARAMETERS                                   
    NO RESONANCE PARAMETERS WERE GIVEN.                           
                                                                  
  2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS                 
                      2200 M/S VALUE       RES. INT.              
        TOTAL            24.50  B            -                    
        ELASTIC          12.50  B            -                    
        CAPTURE          12.00  B          29.0  B                
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  MT=1  TOTAL CROSS SECTION                                       
        BELOW 45 EV, CALCULATED AS SUM OF MT'S = 2 AND 102.       
        ABOVE 45 EV, OPTICAL MODEL CALCULATION WAS MADE WITH      
        CASTHY/2/.  THE POTENTIAL PARAMETERS/3/ USED ARE AS       
        FOLLOWS,                                                  
           V = 41.0 - 0.05*EN                      (MEV)          
           WS= 6.4 - 0.15*SQRT(EN)                 (MEV)          
           WV= 0             , VSO = 7.0           (MEV)          
           R = RSO = 1.31    , RS = 1.38            (FM)          
           A = ASO = 0.47    , B  = 0.47            (FM)          
                                                                  
  MT=2  ELASTIC SCATTERING CROSS SECTION                          
        BELOW 45 EV, THE CONSTANT CROSS SECTION OF 12.5 BARNS WAS 
        ASSUMED, WHICH WAS THE SHAPE ELASTIC SCATTERING CROSS     
        SECTION CALCULATED WITH OPTICAL MODEL. ABOVE THIS ENERGY, 
        OPTICAL MODEL CALCULATION WAS ADOPTED.                    
                                                                  
  MT=4,51-61,91  INELASTIC SCATTERING CROSS SECTIONS.             
        OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH   
        CASTHY/2/.  THE LEVEL SCHEME WAS TAKEN FROM REF. 4.       
                   NO         ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0.0          2 +               
                    1             84.37         2 +               
                    2            215.99         1 -               
                    3            250.78         4 +               
                    4            290.36         3 -               
                    5            433.08         5 -               
                    6            479.30         6 +               
                    7            916.33         0 +               
                    8            965.51         2 +               
                    9            992.65         2 +               
                   10           1052.95         1 -               
                   11           1089.98         2 -               
        LEVELS ABOVE 1187 KEV WERE ASSUMED TO BE OVERLAPPING.     
        THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM REF. 5.      
                                                                  
  MT=16,17,37  (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS  
        CALCULATED WITH EVAPORATION MODEL.                        
                                                                  
  MT=102  CAPTURE CROSS SECTION                                   
        MEASURED THERMAL CROSS SECTION OF 12 BARNS WAS TAKEN      
        FROM REF. 6 , AND 1/V FORM WAS ASSUMED BELOW 45 EV.       
        ABOVE 45 EV, CROSS SECTION WAS CALCULATED WITH CASTHY.    
        THE GAMMA-RAY STRENGTH FUNCTION WAS ESTIMATED FROM        
        GAMMA-GAMMA = 0.040 EV AND LEVEL SPACING = 90 EV.         
                                                                  
  MT=251  MU-L                                                    
        CALCULATED WITH CASTHY.                                   
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-61,91       CALCULATED WITH OPTICAL MODEL.              
  MT=16,17,37         ISOTROPIC IN THE LAB SYSTEM.                
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,37,91      EVAPORATION SPECTRA                         
         OBTAINED FROM LEVEL DENSITY PARAMETERS.                  
                                                                  
REFERENCES                                                        
 1) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).               
 2) IGARASI S.: J.NUCL.SCI.TECHNOL.,12,67 (1975).                 
 3) OHSAWA T., OHTA M.: J. NUCL. SCI. TECHNOL., 18, 408 (1981).   
 4) MARTIN M.J.: NUCL. DATA SHEETS, 49, 83 (1986).                
 5) GILBERT A., CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).   
 6) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL.1, NEUTRON      
    RESONANCE PARAMETERS AND THERMAL CROSS SECTIONS , PART B,     
    Z=61-100", ACADEMIC PRESS (1984).