62-Sm-153

 62-SM-153 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAR02 REV2-FEB02            20020222   
----JENDL-3.3         MATERIAL 6252                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
   ===========================================================    
   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                                                           
90-03 NEW EVALUATION FOR JENDL-3 WAS COMPLETED BY JNDC FPND       
      W.G./1/                                                     
                                                                  
MF = 1  GENERAL INFORMATION                                       
  MT=451 COMMENTS AND DICTIONARY                                  
                                                                  
MF = 2  RESONANCE PARAMETERS                                      
  MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS             
  NO RESOLVED RESONANCE PARAMETERS                                
                                                                  
  UNRESOLVED RESONANCE REGION : 4.4 EV - 100 KEV                  
    THE NEUTRON STRENGTH FUNCTIONS, S0, S1 AND S2 WERE CALCULATED 
    WITH OPTICAL MODEL CODE CASTHY/2/.  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.                                                      
                                                                  
  TYPICAL VALUES OF THE PARAMETERS AT 70 KEV:                     
    S0 = 2.300E-4, S1 = 1.200E-4, S2 = 2.400E-4, SG = 103.E-4,    
    GG = 0.088 EV, R  = 7.146 FM.                                 
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL         426.7                      -                  
      ELASTIC         6.700                    -                  
      CAPTURE       420.0                     717                 
                                                                  
MF = 3  NEUTRON CROSS SECTIONS                                    
  BELOW 4.4 EV, THE CAPTURE AND ELASTIC SCATTERING CROSS SECTIONS 
  WERE ASSUMED TO BE IN 1/V FORM AND CONSTANT, RESPECTIVELY.      
  THE CAPTURE CROSS SECTION AT 0.0253 EV WAS TAKEN FROM REF./3/   
  AND THE SCATTERING CROSS SECTION WAS ESTIMATED FROM R = 7.3 FM. 
  UNRESOLVED RESONANCE PARAMETERS WERE GIVEN IN THE ENERGY RANGE  
  FROM 4.4 EV TO 100 KEV.                                         
                                                                  
  ABOVE 100 KEV, THE SPHERICAL OPTICAL AND STATISTICAL MODEL      
  CALCULATION WAS PERFORMED WITH CASTHY, BY TAKING ACCOUNT OF     
  COMPETING REACTIONS, OF WHICH CROSS SECTIONS WERE CALCULATED    
  WITH PEGASUS/4/ STANDING ON A PREEQUILIBRIUM AND MULTI-STEP     
  EVAPORATION MODEL.  THE OMP'S FOR NEUTRON GIVEN IN TABLE 1 WERE 
  DETERMINED TO REPRODUCE THE TOTAL CROSS SECTION OF NATURAL SM   
  MEASURED BY FOSTER AND GLASGOW/5/, KELLIE ET AL./6/ AND SO ON.  
  THE OMP'S FOR CHARGED PARTICLES ARE AS FOLLOWS:                 
     PROTON   = PEREY/7/                                          
     ALPHA    = HUIZENGA AND IGO/8/                               
     DEUTERON = LOHR AND HAEBERLI/9/                              
     HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/10/            
  PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GILBERT   
  AND CAMERON/11/ WERE EVALUATED BY IIJIMA ET AL./12/  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
  /13/.                                                           
                                                                  
  MT = 1  TOTAL                                                   
    SPHERICAL OPTICAL MODEL CALCULATION WAS ADOPTED.              
                                                                  
  MT = 2  ELASTIC SCATTERING                                      
    CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS).        
                                                                  
  MT = 4, 51 - 91  INELASTIC SCATTERING                           
    SPHERICAL OPTICAL AND STATISTICAL MODEL CALCULATION WAS       
    ADOPTED. THE LEVEL SCHEME WAS BASED ON EVALUATED NUCLEAR      
    STRUCTURE DATA FILE (1987 VERSION)/14/ AND NUCLEAR DATA       
    SHEETS/15/.                                                   
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY                    
           GR.       0.0            3/2 +                         
            1        0.0075         5/2 +                         
            2        0.0358         3/2 -                         
            3        0.0535         7/2 +                         
            4        0.0655         9/2 +                         
            5        0.0909         5/2 -                         
            6        0.0984        11/2 -                         
            7        0.1273         3/2 -                         
            8        0.1742         7/2 -                         
            9        0.1829         5/2 -                         
           10        0.1892        11/2 +                         
           11        0.1946         5/2 +                         
           12        0.1959        13/2 +                         
           13        0.2463        13/2 -                         
           14        0.2623         7/2 +                         
           15        0.2659         7/2 -                         
           16        0.2767         3/2 +                         
           17        0.3211         3/2 +                         
           18        0.3567         5/2 +                         
           19        0.3623         5/2 +                         
           20        0.3710         9/2 -                         
           21        0.4055         3/2 -                         
           22        0.4133        15/2 -                         
           23        0.4149         1/2 +                         
           24        0.4178        17/2 +                         
           25        0.4253        15/2 +                         
           26        0.4471         7/2 +                         
           27        0.4500         5/2 -                         
           28        0.4811         3/2 +                         
      LEVELS ABOVE 0.492 MEV WERE ASSUMED TO BE OVERLAPPING.      
                                                                  
  MT = 102  CAPTURE                                               
    SPHERICAL OPTICAL AND STATISTICAL MODEL CALCULATION WITH      
    CASTHY WAS ADOPTED.  DIRECT AND SEMI-DIRECT CAPTURE CROSS     
    SECTIONS WERE ESTIMATED ACCORDING TO THE PROCEDURE OF BENZI   
    AND REFFO/16/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.       
                                                                  
    THE GAMMA-RAY STRENGTH FUNCTION (1.00E-02) WAS DETERMINED FROM
    THE SYSTEMATICS OF RADIATION WIDTH (0.088 EV) AND THE AVERAGE 
    S-WAVE RESONANCE LEVEL SPACING (8.76 EV) CALCULATED FROM THE  
    LEVEL DENSITY PARAMETERS.                                     
                                                                  
  MT = 16  (N,2N) CROSS SECTION                                   
  MT = 17  (N,3N) CROSS SECTION                                   
  MT = 22  (N,N'A) CROSS SECTION                                  
  MT = 28  (N,N'P) CROSS SECTION                                  
  MT = 32  (N,N'D) CROSS SECTION                                  
  MT =103  (N,P) CROSS SECTION                                    
  MT =104  (N,D) CROSS SECTION                                    
  MT =105  (N,T) CROSS SECTION                                    
  MT =107  (N,ALPHA) CROSS SECTION                                
    THESE REACTION CROSS SECTIONS WERE CALCULATED WITH THE        
    PREEQUILIBRIUM AND MULTI-STEP EVAPORATION MODEL CODE PEGASUS. 
                                                                  
    THE KALBACH'S CONSTANT K (=  25.0) WAS ASSUMED TO BE THE SAME 
    AS THAT OF SM-148.                                            
                                                                  
    FINALLY, THE (N,P) AND (N,ALPHA) CROSS SECTIONS WERE          
    NORMALIZED TO THE FOLLOWING VALUES AT 14.5 MEV:               
      (N,P)          2.88  MB (SYSTEMATICS OF FORREST/17/)        
      (N,ALPHA)      0.97  MB (SYSTEMATICS OF FORREST)            
                                                                  
  MT = 251  MU-BAR                                                
    CALCULATED WITH CASTHY.                                       
                                                                  
MF = 4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS               
  LEGENDRE POLYNOMIAL COEFFICIENTS FOR ANGULAR DISTRIBUTIONS ARE  
  GIVEN IN THE CENTER-OF-MASS SYSTEM FOR MT=2 AND DISCRETE INELAS-
  TIC LEVELS, AND IN THE LABORATORY SYSTEM FOR MT=91.  THEY WERE  
  CALCULATED WITH CASTHY.  FOR OTHER REACTIONS, ISOTROPIC DISTRI- 
  BUTIONS IN THE LABORATORY SYSTEM WERE ASSUMED.                  
                                                                  
MF = 5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                
  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE CALCULATED WITH 
  PEGASUS FOR INELASTIC SCATTERING FROM OVERLAPPING LEVELS AND FOR
  OTHER NEUTRON EMITTING REACTIONS.                               
                                                                  
TABLE 1  NEUTRON OPTICAL POTENTIAL PARAMETERS                     
                                                                  
                DEPTH (MEV)       RADIUS(FM)    DIFFUSENESS(FM)   
         ----------------------   ------------  ---------------   
        V  = 46.96-0.0172E        R0 = 6.365    A0 = 0.655        
        WS = 8.455                RS = 7.702    AS = 0.448        
        VSO= 7.0                  RSO= 6.846    ASO= 0.6          
  THE FORM OF SURFACE ABSORPTION PART IS DER. WOODS-SAXON TYPE.   
                                                                  
TABLE 2  LEVEL DENSITY PARAMETERS                                 
                                                                  
 NUCLIDE  SYST A(1/MEV)  T(MEV)    C(1/MEV)  EX(MEV)   PAIRING    
 ---------------------------------------------------------------  
 60-ND-149     2.657E+01 4.750E-01 1.192E+01 5.636E+00 1.180E+00  
 60-ND-150     2.415E+01 5.280E-01 1.867E+00 7.314E+00 2.290E+00  
 60-ND-151     2.618E+01 4.800E-01 1.152E+01 5.656E+00 1.180E+00  
 60-ND-152  *  2.361E+01 5.242E-01 1.915E+00 6.885E+00 2.100E+00  
                                                                  
 61-PM-150     2.270E+01 3.800E-01 7.943E+00 1.973E+00 0.0        
 61-PM-151     2.882E+01 4.260E-01 8.842E+00 4.956E+00 1.110E+00  
 61-PM-152  *  2.440E+01 5.242E-01 1.481E+02 5.009E+00 0.0        
 61-PM-153     2.285E+01 4.950E-01 7.324E+00 4.895E+00 9.200E-01  
                                                                  
 62-SM-151     2.687E+01 5.000E-01 2.313E+01 6.327E+00 1.220E+00  
 62-SM-152     2.375E+01 5.470E-01 2.365E+00 7.669E+00 2.330E+00  
 62-SM-153     2.572E+01 5.160E-01 2.101E+01 6.405E+00 1.220E+00  
 62-SM-154     2.190E+01 5.600E-01 1.960E+00 7.188E+00 2.140E+00  
 ---------------------------------------------------------------  
  SYST:  * = LDP'S WERE DETERMINED FROM SYSTEMATICS.              
                                                                  
 SPIN CUTOFF PARAMETERS WERE CALCULATED AS 0.146*SQRT(A)*A**(2/3).
 IN THE CASTHY CALCULATION, SPIN CUTOFF FACTORS AT 0 MEV WERE     
 ASSUMED TO BE 10.66 FOR SM-153 AND 9.75 FOR SM-154.              
                                                                  
REFERENCES                                                        
 1) KAWAI, M. ET AL.: PROC. INT. CONF. ON NUCLEAR DATA FOR SCIENCE
    AND TECHNOLOGY, MITO, P. 569 (1988).                          
 2) IGARASI, S.: J. NUCL. SCI. TECHNOL., 12, 67 (1975).           
 3) MUGHABGHAB, S.F.: "NEUTRON CROSS SECTIONS, VOL. I, PART B",   
    ACADEMIC PRESS (1984).                                        
 4) IIJIMA, S. ET AL.: JAERI-M 87-025, P. 337 (1987).             
 5) FOSTER, D.G. JR. AND GLASGOW, D.W.: PHYS. REV., C3, 576       
    (1971).                                                       
 6) KELLIE, J.D., HALL, S.J. AND CRAWFORD, G.I. ET AL.:           
    J. PHYS., A7, 1758 (1974).                                    
 7) PEREY, F.G: PHYS. REV. 131, 745 (1963).                       
 8) HUIZENGA, J.R. AND IGO, G.: NUCL. PHYS. 29, 462 (1962).       
 9) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).    
10) BECCHETTI, F.D., JR. AND GREENLEES, G.W.: POLARIZATION        
    PHENOMENA IN NUCLEAR REACTIONS ((EDS) H.H. BARSHALL AND       
    W. HAEBERLI), P. 682, THE UNIVERSITY OF WISCONSIN PRESS.      
    (1971).                                                       
11) GILBERT, A. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446      
    (1965).                                                       
12) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).     
13) GRUPPELAAR, H.: ECN-13 (1977).                                
14) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE (JUNE 1987).     
15) NUCLEAR DATA SHEETS, 37, 487 (1982).                          
16) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
17) FORREST, R.A.: AERE-R 12419 (1986).