88-Ra-226

 88-RA-226 TIT        EVAL-AUG88 N.TAKAGI                         
                      DIST-SEP89 REV2-NOV93                       
----JENDL-3.2         MATERIAL 8834                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
88-08 NEW EVALUATION WAS MADE BY N. TAKAGI (TOKYO INSTITUTE OF    
      TECHNOLOGY, TIT)/1/                                         
93-11 JENDL-3.2.                                                  
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (3,1), (3,18)        BELOW 6 MEV.                           
     ***********************************************************  
                                                                  
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451   COMMENT AND DICTIONARY                                 
  MT=452   NUMBER OF NEUTRONS PER FISSION                         
            EVALUATED WITH SEMI EMPIRICAL FORMULA OF HOWERTON/2/. 
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151   RESOLVED RESONANCE PARAMETERS : 1.0E-5 EV TO 1000 EV.  
           MULTI-LEVEL BREIT-WIGNER FORMULA WAS ADOPTED.          
           PARAMETERS WERE TAKEN FROM THOSE BY IVANOV/3/.         
           NO FISSION WIDTH WAS GIVEN FOR ALL THE RESONANCES.     
                AVERAGE GAM-G = 0.0258 EV                         
                EFFECTIVE SCATTERING RADIUS = 9.60 FM             
                                                                  
  2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS                 
                      2200 M/S VALUE       RES. INT.              
        TOTAL           22.58    B             -                  
        ELASTIC          9.80    B             -                  
        FISSION          7.0E-6  B          0.0119 B              
        CAPTURE         12.78    B          285.6  B              
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  MT=1  TOTAL CROSS SECTION                                       
        BELOW 1 KEV, CROSS SECTION WAS REPRESENTED WITH RESONANCE 
        PARAMETERS. ABOVE 1 KEV, OPTICAL MODEL CALCULATION WAS    
        MADE WITH CASTHY/4/.  THE POTENTIAL PARAMETERS/5/ 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 1 KEV, CROSS SECTION WAS REPRESENTED WITH RESONANCE 
        PARAMETERS. ABOVE 1 KEV, OPTICAL MODEL CALCULATION WAS    
        ADOPTED.                                                  
                                                                  
  MT=4,51-66,91  INELASTIC SCATTERING CROSS SECTIONS.             
        OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH   
        CASTHY/4/.  THE LEVEL SCHEME WAS TAKEN FROM REF./6/       
                   NO         ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0.0           0 +              
                    1             67.67          2 +              
                    2            211.54          4 +              
                    3            253.73          1 -              
                    4            321.54          3 -              
                    5            416.60          6 +              
                    6            446.20          5 -              
                    7            626.90          7 -              
                    8            650.00          0 +              
                    9            669.40          8 +              
                   10            824.60          0 +              
                   11            857.90          9 -              
                   12            873.70          2 +              
                   13            960.00         10 +              
                   14           1048.60          1 -              
                   15           1070.50          2 -              
                   16           1134.00         11 -              
        LEVELS ABOVE 1446 KEV WERE ASSUMED TO BE OVERLAPPING.     
        THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM REF./7/      
                                                                  
  MT=16,17,37  (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS  
        CALCULATED WITH EVAPORATION MODEL.                        
                                                                  
  MT=18  FISSION CROSS SECTION                                    
        MEASURED THERMAL CROSS SECTION OF 7 MICRO-BARN WAS TAKEN  
        FROM REF./8/, AND 1/V FORM WAS ASSUMED BELOW 10 EV.  FOR  
        ENERGY REGION ABOVE 1 MEV, THE EVALUATION WAS BASED ON    
        EXPERIMENTAL DATA /9,10,11,12/, AND BETWEEN 15 EV AND     
        FISSION THRESHOLD, CROSS SECTION WAS ASSUMED TO BE THE    
        SAME AS THE VALUE AT 15 EV.                               
                                                                  
  MT=102  CAPTURE CROSS SECTION                                   
        BELOW 1 KEV, CROSS SECTION WAS REPRESENTED WITH RESONANCE 
        PARAMETERS.  ABOVE 1 KEV, IT WAS CALCULATED WITH CASTHY.  
        THE GAMMA-RAY STRENGTH FUNCTION WAS ESTIMATED FROM        
        GAMMA-GAMMA = 0.040 EV AND LEVEL SPACING = 30.3 EV.       
                                                                  
  MT=251  MU-L                                                    
        CALCULATED WITH CASTHY.                                   
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-66,91       CALCULATED WITH OPTICAL MODEL.              
  MT=16,17,18,37      ISOTROPIC IN THE LAB SYSTEM.                
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,37,91      EVAPORATION SPECTRA                         
         OBTAINED FROM LEVEL DENSITY PARAMETERS.                  
                                                                  
  MT=18               MAXWELLIAN FISSION SPECTRUM.                
        TEMPERATURE WAS ESTIMATED FROM Z**2/A DEPENDENCE/13/.     
                                                                  
REFERENCES                                                        
 1) TAKAGI N. ET AL.: J. NUCL. SCI. TECHNOL., 27, 853 (1990).     
 2) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).               
 3) IVANOV R.N. ET AL.: AT. ENERG., 42, 505 (1977).               
 4) IGARASI S. AND FUKAFORI T.: JAERI 1321 (1991).                
 5) OHSAWA T., OHTA M.: J. NUCL. SCI. TECHNOL., 18, 408 (1981).   
 6) ELLIS-AKOVALI Y.A.: NUCL. DATA SHEETS, 50, 229 (1987).        
 7) GILBERT A., CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).   
 8) NAKAHARA H. ET AL.: J. INORG. NUCL. CHEM., 38, 203 (1976).    
 9) NOBLES R.A ET AL.: NUCL. PHYS., 5, 211 (1958).                
10) BABENKO JU.A. ET AL.: YAD. FIZ., 7, 269 (1968).               
11) ZHAGROV E.A. ET AL.: NUCL. PHYS., A213, 436 (1973).           
12) NEMILOV YU.A. ET AL.: YAD. FIZ., 37, 819 (1983).              
13) SMITH A.B. ET AL.: ANL/NDM-50 (1979).