51-Sb- 0

 51-SB-  0 JNDC       EVAL-MAR89 JNDC FP NUCLEAR DATA W.G.        
                      DIST-OCT89 REV2-FEB94                       
----JENDL-3.2         MATERIAL 5100                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
89-03 DATA WERE CONSTRUCTED WITH THOSE FOR SB-121 AND SB-123 WHICH
      WERE EVALUATED BY JNDC FP NUCLEAR DATA W.G./1/.             
90-07 UNRESOLVED RESONANCE PARAMETERS AND MF=3, MT=251 WERE       
      MODIFIED.                                                   
90-10 SPECTRA AT THRESHOLD ENERGIES WERE MODIFIED.                
94-02 JENDL-3.2                                                   
      CAPTURE CROSS SECTION MODIFIED BY JNDC FPND WG.             
      OTHER DATA WERE ADOPTED FROM JENDL FUSION FILE.             
      COMPILED BY T.NAKAGAWA                                      
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      ALL CROSS SECTIONS EXCEPT (3,105).                          
          (3,32) AND (3,33) WERE DELETED.                         
      ALL ANGULAR DISTRIBUTIONS EXCEPT FOR (4,2).                 
      ALL ENERGY DISTRIBUTIONS.                                   
     ***********************************************************  
     -------------------------------------------------------------
      JENDL FUSION FILE /2/  (AS OF FEB. 1994)                    
            EVALUATED BY K.KOSAKO (NEDAC) AND S. CHIBA (NDC/JAERI)
            COMPILED  BY K.KOSAKO.                                
                                                                  
      -  THE INELASTIC SCATTERING CROSS SECTIONS AND ANGULAR      
         DISTRIBUTIONS OF INELASTICALLY SCATTERED NEUTRONS (EXCEPT
         CONTINUUM INELASTIC) WERE CALCULATED WITH CASTHY2Y AND   
         DWUCKY IN SINCROS-II SYSTEM/3/ INCLUDING CONTRIBUTIONS   
         FROM DIRECT REACTIONS.                                   
      -  THE (N,2N), (N,3N), (N,NA), (N,NP), (N,P), (N,D) AND     
         (N,A) REACTION CROSS SECTIONS (MT=16, 17, 22, 28, 103,   
         104, 107) WERE CALCULATED BY EGNASH2 IN THE SINCROS-II.  
      -  THE (N,T) REACTION CROSS SECTION, RESONANCE PARAMETERS   
         AND ANG. DISTRIBUTIONS OF ELASTICALLY SCATTERED NEUTRONS 
         WERE TAKEN FROM JENDL-3.1.                               
      -  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE REPLACED 
         BY THOSE CALCULATED BY EGNASH2.  THE DDX'S OF THE        
         CONTINUUM NEUTRONS WERE CALCULATED BY KUMABE'S SYSTEMA-  
         TICS /4/ USING F15TOB /2/.  THE PRECOMPOUND/COMPOUND     
         RATIO WAS CALCULATED BY THE SINCROS- II CODE SYSTEM.     
      -  OPTICAL-MODEL, LEVEL DENSITY AND OTHER PARAMETERS USED IN
         THE SINCROS-II CALCULATION ARE DESCRIBED IN REF./3/.     
         LEVEL SCHEMES WERE DETERMINED ON THE BASIS OF ENSDF/5/.  
     -------------------------------------------------------------
                                                                  
                                                                  
MF = 1  GENERAL INFORMATION                                       
  MT=451 COMMENTS AND DICTIONARY                                  
                                                                  
MF = 2  RESONANCE PARAMETERS                                      
  MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS             
  RESOLVED RESONANCE PARAMETERS (MLBW FORMULA)                    
  1) SB-121 : BELOW 2 KEV                                         
       EVALUATION WAS MADE ON THE BASIS OF DATA MEASURED BY       
       OHKUBO ET AT./6,7/, BOLOTIN AND CHRIEN/8/, WYNCHANK ET     
       AL./9/, MURADJAN ET AL./10/ AND ADAMCHUK ET AL./11/.       
       ANGULAR MOMENTUM L AND SPIN J WERE BASED ON THE DATA BY    
       BELYAEV ET AL./12/, BAHT ET AL./13/ AND CAUVIN ET AL./14/. 
       THE AVERAGE RADIATIVE CAPTURE WIDTH OF 0.089 EV WAS        
       ASSUMED.                                                   
  2) SB-123 : BELOW 2.5 KEV                                       
       EVALUATION WAS MADE ON THE BASIS OF THE DATA MEASURED BY   
       OHKUBO ET AL./6,15/, STOLVY AND HARVEY/16/, BOLOTIN AND    
       CHRIEN/8/, WYNCHANK ET AL./9/, MURADJAN ET AL./10/ AND     
       ADAMCHUK ET AL./11/.  ANGULAR MOMENTUM L AND SPIN J WERE   
       BASED ON THE DATA BY BAHT ET AL./13/ AND CAUVIN ET AL./14/.
       THE AVERAGE RADIATIVE CAPTURE WIDTH OF 0.098 EV WAS        
       ASSUMED.                                                   
  UNRESOLVED RESONANCE REGION : UP TO 100 KEV                     
    THE NEUTRON STRENGTH FUNCTIONS, S0, S1 AND S2 WERE CALCULATED 
    WITH OPTICAL MODEL CODE CASTHY/17/.  THE OBSERVED LEVEL       
    SPACING WAS DETERMINED TO REPRODUCE THE CAPTURE CROSS SECTION 
    CALCULATED WITH CASTHY.  THE EFFECTIVE SCATTERING RADIUS WAS  
    OBTAINED FROM FITTING TO THE CALCULATED TOTAL CROSS SECTION AT
    100 KEV.                                                      
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL           8.943                    -                  
      ELASTIC         3.722                    -                  
      CAPTURE         5.221                   175                 
                                                                  
MF = 3  NEUTRON CROSS SECTIONS                                    
  BELOW 100 KEV, RESONANCE PARAMETERS WERE GIVEN.                 
                                                                  
  FOR JENDL-3.1, ABOVE 100 KEV, THE SPHERICAL OPTICAL AND         
  STATISTICAL MODEL CALCULATION WAS PERFORMED WITH CASTHY/17/, BY 
  TAKING ACCOUNT OF COMPETING REACTIONS, OF WHICH CROSS SECTIONS  
  WERE CALCULATED WITH PEGASUS/18/ STANDING ON A PREEQUILIBRIUM   
  AND MULTI-STEP EVAPORATION MODEL.  THE OMP'S FOR NEUTRON GIVEN  
  IN TABLE 1 WERE ADOPTED FROM IIJIMA AND KAWAI/19/ BY MODIFYING  
  RADIUS PARAMETER OF THE SPIN-ORBIT TERM.  THE OMP'S FOR CHARGED 
  PARTICLES ARE AS FOLLOWS:                                       
     PROTON   = PEREY/20/                                         
     ALPHA    = HUIZENGA AND IGO/21/                              
     DEUTERON = LOHR AND HAEBERLI/22/                             
     HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/23/            
  PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GIRBERT   
  AND CAMERON/24/ WERE EVALUATED BY IIJIMA ET AL./25/.  MORE      
  EXTENSIVE DETERMINATION AND MODIFICATION WERE MADE IN THE       
  PRESENT WORK.  TABLE 2 SHOWS THE LEVEL DENSITY PARAMETERS USED  
  IN THE PRESENT CALCULATION.  ENERGY DEPENDENCE OF SPIN CUT-OFF  
  PARAMETER IN THE ENERGY RANGE BELOW E-JOINT IS DUE TO GRUPPELAAR
  /26/.                                                           
                                                                  
  FOR JENDL-3.2, ALL CROSS SECTION DATA EXCEPT FOR THE ELASTIC    
  SCATTERING, CAPTURE AND (N,T) WERE ADOPTED FROM JENDL FUSION    
  FILE.  THE CALCULATION WAS MADE WITH SINCROS-II SYSTEM/3/ BY    
  ADOPTING WALTER-GUSS OMP MODIFIED BY YAMAMURO/3/ FOR NEUTRON,   
  PEREY OMP /27/ FOR PROTON, LEMOS OMP MODIFIED BY ARTHUR AND     
  YOUNG/28/ FOR ALPHA, LOHR-HAEBERLI OMP/29/ FOR DEUTERON,        
  BECCHETTII-GREENLEES OMP/30/ FOR TRITON AND HE-3, AND STANDARD  
  LEVEL DENSITY PARAMETERS OF SINCROS-II SYSTEM.                  
                                                                  
  MT = 1  TOTAL                                                   
    SPHERICAL OPTICAL MODEL CALCULATION WAS ADOPTED IN THE ENERGY 
    RANGES BELOW 500 KEV.  BETWEEN 500 KEV AND 11.5 MEV, SPLINE   
    FITTING TO THE EXPERIMENTAL DATA /31,32/ WAS PERFORMED.  ABOVE
    THIS, EXPERIMENTAL DATA WERE CONNECTED BY EYE-GUIDING.        
                                                                  
  MT = 2  ELASTIC SCATTERING                                      
    CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS).        
                                                                  
  MT = 4, 51 - 91  INELASTIC SCATTERING                           
    THE CROSS SECTIONS WERE TAKEN FROM JENDL FUSION FILE.  THE    
    LEVEL SCHEME WAS BASED ON REF./5/  CONTRIBUTIONS OF THE       
    DIRECT PROCESS WERE CALCULATED FOR THE LEVELS MARKED WITH '*'.
                                                                  
          --- SB-121 ---                   --- SB-123 ---         
    NO. MT  ENERGY(MEV)  J-PARITY    NO. MT  ENERGY(MEV)  J-PARITY
    GR.       0.0        5/2 +       GR.       0.0        7/2 +   
     1  51    0.0371     7/2 + *      1  52    0.1603     5/2 + * 
     2  53    0.5076     3/2 + *      2  54    0.5418     3/2 + * 
     3  55    0.5731     1/2 + *      3  56    0.7128     1/2 +   
     4  57    0.9470     9/2 + *      4  59    1.0302     9/2 + * 
     5  58    1.0240     7/2 + *      5  61    1.0886     9/2 + * 
     6  60    1.0354     9/2 +        6  64    1.1813     7/2 + * 
     7  62    1.1393    11/2 +        7  65    1.2609     5/2 + * 
     8  63    1.1447     9/2 + *      8  66    1.3374     7/2 + * 
     9  67    1.3862     9/2 +                                    
    10  68    1.4075     5/2 +                                    
    11  69    1.4105     7/2 +                                    
    12  70    1.4272     9/2 + *                                  
    13  71    1.4480     1/2 -                                    
       OVERLAPPING LEVELS WERE ASSUMED ABOVE 1.449 MEV FOR SB-121 
       AND ABOVE 1.338 MEV FOR SB-123.                            
                                                                  
  MT = 102  CAPTURE                                               
    SPHERICAL OPTICAL AND STATISTICAL MODEL CALCULATION WITH      
    CASTHY/17/ WAS ADOPTED.  DIRECT AND SEMI-DIRECT CAPTURE CROSS 
    SECTIONS WERE ESTIMATED ACCORDING TO THE PROCEDURE OF BENZI   
    AND REFFO/33/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.       
                                                                  
    THE GAMMA-RAY STRENGTH FUNCTIONS WERE ADJUSTED TO REPRODUCE   
    THE CAPTURE CROSS SECTIONS.                                   
                CROSS SECTION (1 MEV)     STRENGTH FUNCTION       
       SB-121         0.110 BARN               54.5E-4            
       SB-123         0.084 BARN               24.2E-4            
                                                                  
  MT = 16, 17, 22, 28, 103, 104, 107                              
           (N,2N), (N,3N), (N,N'A), (N,N'P), (N,P), (N,D)         
           AND (N,ALPHA) CROSS SECTIONS                           
   ADOPTED FROM JENDL FUSION FILE.  THEORETICAL CALCULATION WAS   
   MADE WITH SINCROS-II FOR EACH ISOTOPES, AND THE RESULTS WERE   
   NORMALIZED TO EXPERIMENTAL DATA.                               
                                                                  
  MT = 105   (N,T) CROSS SECTIONS                                 
    CALCULATED WITH THE PREEQUILIBRIUM AND MULTI-STEP EVAPORATION 
    MODEL CODE PEGASUS/18/.                                       
                                                                  
    THE KALBACH'S CONSTANTS WERE ESTIMATED BY THE FORMULA DERIVED 
    FROM KIKUCHI-KAWAI'S FORMALISM/34/ AND LEVEL DENSITY          
    PARAMETERS.                                                   
        SB-121: 145.3,      SB-123: 174.0                         
                                                                  
  MT = 251  MU-BAR                                                
    CALCULATED WITH CASTHY/17/.                                   
                                                                  
MF = 4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS               
 MT=2                                                             
   CALCULATED WITH THE CASTHY CODE/17/.                           
 MT=16, 17, 22, 28, 51-91                                         
   TAKEN FROM JENDL FUSION FILE.                                  
                                                                  
MF = 5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                
 MT=16, 17, 22, 28, 51-91                                         
   TAKEN FROM JENDL FUSION FILE.                                  
                                                                  
                                                                  
<< THE PARAMETERS USED IN THE CASTHY AND PEGASUS CALCULATIONS.>>  
                                                                  
TABLE 1  NEUTRON OPTICAL POTENTIAL PARAMETERS                     
                                                                  
                DEPTH (MEV)       RADIUS(FM)    DIFFUSENESS(FM)   
         ----------------------   ------------  ---------------   
        V  = 47.64-0.473E         R0 = 6.256    A0 = 0.62         
        WS = 9.744                RS = 6.469    AS = 0.35         
        WSO= 7.0                  RSO= 6.241    ASO= 0.62         
                                                                  
TABLE 2  LEVEL DENSITY PARAMETERS                                 
                                                                  
 NUCLIDE  SYST A(/MEV)   T(MEV)    C(/MEV)   EX(MEV)   PAIRING    
 ---------------------------------------------------------------  
 49-IN-117     1.678E+01 6.010E-01 2.387E+00 5.208E+00 1.150E+00  
 49-IN-118  *  1.804E+01 6.064E-01 3.111E+01 4.636E+00 0.0        
 49-IN-119     1.940E+01 5.340E-01 2.195E+00 4.999E+00 1.240E+00  
 49-IN-120  *  1.757E+01 6.016E-01 2.330E+01 4.366E+00 0.0        
 49-IN-121     1.601E+01 6.060E-01 1.119E+00 5.277E+00 1.430E+00  
 49-IN-122  *  1.707E+01 5.968E-01 1.737E+01 4.092E+00 0.0        
                                                                  
 50-SN-118     1.633E+01 6.140E-01 3.341E-01 6.448E+00 2.340E+00  
 50-SN-119     1.635E+01 5.990E-01 1.772E+00 5.050E+00 1.190E+00  
 50-SN-120     1.595E+01 6.540E-01 4.691E-01 7.083E+00 2.430E+00  
 50-SN-121     1.630E+01 6.100E-01 2.010E+00 5.217E+00 1.190E+00  
 50-SN-122     1.434E+01 7.060E-01 3.423E-01 7.416E+00 2.620E+00  
 50-SN-123     1.509E+01 6.870E-01 3.062E+00 6.032E+00 1.190E+00  
                                                                  
 51-SB-119  *  1.858E+01 6.040E-01 5.801E+00 5.944E+00 1.150E+00  
 51-SB-120  *  1.834E+01 6.016E-01 3.366E+01 4.659E+00 0.0        
 51-SB-121     1.730E+01 5.740E-01 1.715E+00 5.022E+00 1.240E+00  
 51-SB-122     1.772E+01 5.500E-01 1.346E+01 3.517E+00 0.0        
 51-SB-123     1.585E+01 6.213E-01 1.285E+00 5.469E+00 1.430E+00  
 51-SB-124     1.696E+01 5.600E-01 1.090E+01 3.433E+00 0.0        
 ---------------------------------------------------------------  
  SYST:  * = LDP'S WERE DETERMINED FROM SYSTEMATICS.              
                                                                  
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