62-Sm-148

 62-SM-148 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 6237                               
-----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                                                           
84-10 EVALUATION FOR JENDL-2 WAS MADE BY JNDC FPND W.G./1/        
90-03 MODIFICATION FOR JENDL-3 WAS MADE/2/.                       
93-11 JENDL-3.2 WAS MADE BY JNDC FPND W.G.                        
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (2,151)         UPPER BOUNDARY OF THE RESOLVED RESONANCE    
                      REGION WAS CHANGED FROM 8 KEV TO 5.5 KEV.   
      (3,2), (3,4)    EFFECTS OF MODIFICATION OF PARTIAL INELA-   
                      STIC AND CAPTURE CROSS SECTIONS.            
      (3,51), (3,52), (4,51), (4,52)                              
                      DIRECT COMPONENTS ADDED.                    
      (3,53-61), (3,91) AND THEIR ANGULAR DISTRIBUTIONS           
                      EFFECTS OF RENORMALIZATION OF CAPTURE CROSS 
                      SECTION.                                    
      (3,102)         RENORMALIZATION                             
     ***********************************************************  
                                                                  
                                                                  
MF = 1  GENERAL INFORMATION                                       
  MT=451 COMMENTS AND DICTIONARY                                  
                                                                  
MF = 2  RESONANCE PARAMETERS                                      
  MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS             
  RESOLVED RESONANCE REGION (MLBW FORMULA) : BELOW 5.5 KEV        
    RESONANCE PARAMETERS WERE NEWLY EVALUATED ON THE BASIS OF THE 
    DATA MEASURED BY MIZUMOTO AND ZHAO/3,4/.                      
      RESONANCE ENERGIES AND NEUTRON WIDTHS WERE TAKEN FROM THE   
    TRANSMISSION MEASURMENTS BY MIZUMOTO AND ZHAO.  RADIATION     
    WIDTH OF 0.06 EV USED FOR THEIR ANALYSIS WAS ADOPTED.  A      
    NEGATIVE RESONANCE WAS ADDED SO AS TO REPRODUCE THE THERMAL   
    CAPTURE CROSS SECTION GIVEN BY MUGHABGHAB/5/.                 
                                                                  
  UNRESOLVED RESONANCE REGION : 5.5 KEV - 100 KEV                 
    THE NEUTRON STRENGTH FUNCTIONS, S0 AND S1 WERE BASED ON THE   
    COMPILATION OF MUGHABGHAB, AND S2 WAS CALCULATED WITH OPTICAL 
    MODEL CODE CASTHY/6/.  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.
    THE RADIATION WIDTH GG WAS BASED ON THE SYSTEMATICS OF        
    MEASURED VALUES FOR NEIGHBORING NUCLIDES.                     
                                                                  
  TYPICAL VALUES OF THE PARAMETERS AT 70 KEV:                     
    S0 = 3.800E-4, S1 = 1.900E-4, S2 = 2.200E-4, SG = 4.97E-4,    
    GG = 0.065 EV, R  = 5.150 FM.                                 
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL           3.4098                   -                  
      ELASTIC         0.9966                   -                  
      CAPTURE         2.4132                   45.2               
                                                                  
MF = 3  NEUTRON CROSS SECTIONS                                    
  BELOW 100 KEV, RESONANCE PARAMETERS WERE GIVEN.                 
  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/7/ 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/8/, KELLIE ET AL./9/ AND SO      
  ON.  THE OMP'S FOR CHARGED PARTICLES ARE AS FOLLOWS:            
     PROTON   = PEREY/10/                                         
     ALPHA    = HUIZENGA AND IGO/11/                              
     DEUTERON = LOHR AND HAEBERLI/12/                             
     HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/13/            
  PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GILBERT   
  AND CAMERON/14/ WERE EVALUATED BY IIJIMA ET AL./15/  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
  /16/.                                                           
                                                                  
  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 TAKEN FROM REF./17/.           
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY (DIRECT)           
           GR.       0.0             0  +                         
            1        0.5510          2  +         *               
            2        1.1620          3  -         *               
            3        1.1800          4  +                         
            4        1.4300          0  +                         
            5        1.4530          2  +                         
            6        1.4650          1  -                         
            7        1.5950          5  -                         
            8        1.6490          2  +                         
            9        1.6630          2  +                         
           10        1.7330          4  +                         
           11        1.8940          4  +                         
      LEVELS ABOVE 1.906 MEV WERE ASSUMED TO BE OVERLAPPING.      
                                                                  
    FOR THE LEVELS WITH AN ASTERISK, THE CONTRIBUTION OF DIRECT   
    INELASTIC SCATTERING CROSS SECTIONS WAS CALCULATED BY THE     
    DWUCK-4 CODE/18/.  DEFORMATION PARAMETERS (BETA2=0.0202) AND  
    BETA3=0.0251) WERE BASED ON THE DATA COMPILED BY RAMAN ET     
    AL./19/ AND SPEAR/20/, RESPECTIVELY.                          
                                                                  
  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/21/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.       
                                                                  
    THE GAMMA-RAY STRENGTH FUNCTION (4.73E-04) WAS ADJUSTED TO    
    REPRODUCE THE CAPTURE CROSS SECTION OF 185 MILLI-BARNS AT 50  
    KEV MEASURED BY WISSHAK ET AL./22/                            
                                                                  
  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 = 33  (N,N'T) CROSS SECTION                                  
  MT =103  (N,P) CROSS SECTION                                    
  MT =104  (N,D) CROSS SECTION                                    
  MT =105  (N,T) CROSS SECTION                                    
  MT =106  (N,HE3) 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 DETERMINED TO REPRODUCE
    ENERGY DEPENDENCE OF THE (N,2N) CROSS SECTION MEASURED BY     
    FREHAUT ET AL./23/                                            
                                                                  
    FINALLY, THE (N,P) AND (N,ALPHA) CROSS SECTIONS WERE          
    NORMALIZED TO THE FOLLOWING VALUES AT 14.5 MEV:               
      (N,P)          8.00  MB (RECOMMENDED BY FORREST/24/)        
      (N,ALPHA)      3.83  MB (SYSTEMATICS OF FORREST/24/)        
                                                                  
  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 = 6.295    A0 = 0.655        
        WS = 8.455                RS = 7.617    AS = 0.448        
        VSO= 7.0                  RSO= 6.771    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-144     1.771E+01 5.640E-01 4.792E-01 5.691E+00 1.940E+00  
 60-ND-145     2.054E+01 5.120E-01 2.465E+00 4.869E+00 1.180E+00  
 60-ND-146     2.019E+01 5.660E-01 1.121E+00 6.714E+00 2.100E+00  
 60-ND-147     2.398E+01 4.850E-01 5.510E+00 5.235E+00 1.180E+00  
                                                                  
 61-PM-145  *  1.769E+01 5.411E-01 2.780E+00 4.120E+00 7.600E-01  
 61-PM-146  *  1.942E+01 5.387E-01 2.241E+01 3.849E+00 0.0        
 61-PM-147     2.192E+01 4.913E-01 4.801E+00 4.589E+00 9.200E-01  
 61-PM-148     2.227E+01 4.300E-01 1.420E+01 2.672E+00 0.0        
                                                                  
 62-SM-146     1.871E+01 5.117E-01 2.497E-01 5.159E+00 1.980E+00  
 62-SM-147     2.275E+01 4.770E-01 2.660E+00 4.823E+00 1.220E+00  
 62-SM-148     2.097E+01 5.505E-01 1.055E+00 6.694E+00 2.140E+00  
 62-SM-149     2.325E+01 5.052E-01 5.886E+00 5.504E+00 1.220E+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 5.943 FOR SM-148 AND 5.300 FOR SM-149.             
                                                                  
REFERENCES                                                        
 1) AOKI, T. ET AL.: PROC. INT. CONF. ON NUCLEAR DATA FOR BASIC   
    AND APPLIED SCIENCE, SANTA FE., VOL. 2, P.1627 (1985).        
 2) KAWAI, M. ET AL.: J. NUCL. SCI. TECHNOL., 29, 195 (1992).     
 3) MIZUMOTO, M. AND ZHAO, W.R.: JAERI-M 86-112, 168 (1986).      
 4) ZHAO, W.R. AND MIZUMOTO, M.: PRIVATE COMMUNICATION (1986).    
 5) MUGHABGHAB, S.F.: "NEUTRON CROSS SECTIONS, VOL. I, PART B",   
    ACADEMIC PRESS (1984).                                        
 6) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).              
 7) IIJIMA, S. ET AL.: JAERI-M 87-025, P. 337 (1987).             
 8) FOSTER, D.G. JR. AND GLASGOW, D.W.: PHYS. REV., C3, 576       
    (1971).                                                       
 9) KELLIE, J.D., HALL, S.J. AND CRAWFORD, G.I. ET AL.:           
    J. PHYS., A7, 1758 (1974).                                    
10) PEREY, F.G: PHYS. REV. 131, 745 (1963).                       
11) HUIZENGA, J.R. AND IGO, G.: NUCL. PHYS. 29, 462 (1962).       
12) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).    
13) 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).                                                       
14) GILBERT, A. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446      
    (1965).                                                       
15) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).     
16) GRUPPELAAR, H.: ECN-13 (1977).                                
17) MATSUMOTO, J.: PRIVATE COMMUNICATION (1981).                  
18) KUNZ, P.D.: PRIVATE COMMUNICATION.                            
19) RAMAN, S., ET AL.: ATOM. DATA AND NUCL. DATA TABLES 36, 1     
    (1987)                                                        
20) SPEAR, R.H.: ATOM. DATA AND NUCL. DATA TABLE, 42, 55 (1989).  
21) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
22) WISSHAK, K., ET AL.: KFK 5067 (1992).                         
23) FREHAUT, J., ET AL.: SYMP. ON NEUTRON CROSS SECTIONS FROM     
    10-50 MEV, BNL, P.399 (1980).                                 
24) FORREST, R.A.: AERE-R 12419 (1986).