62-Sm-144

 62-SM-144 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-SEP90 REV2-NOV93                       
----JENDL-3.2         MATERIAL 6225                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
90-03 NEW EVALUATION FOR JENDL-3 WAS COMPLETED BY JNDC FPND       
      W.G./1/                                                     
93-11 JENDL-3.2 WAS MADE BY JNDC FPND W.G.                        
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (2,151)        RESOLVED RESONANCE PARAMETERS BASED ON A     
                     RECENT EXPERIMENTAL REPORT.                  
      (3,1), (3,2), (3,4), (3,51-91), (3,102)                     
                     RENORMALIZATION OF CAPTURE AND RECALCU-      
                     LATION OF DIRECT INELASTIC PROCESS.          
      (4,51-91)                                                   
     ***********************************************************  
                                                                  
                                                                  
MF = 1  GENERAL INFORMATION                                       
  MT=451 COMMENTS AND DICTIONARY                                  
                                                                  
MF = 2  RESONANCE PARAMETERS                                      
  MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS             
    THE RESOLVED RESONANCE PARAMETERS WERE EVALUATED ON THE BASIS 
    OF THE DATA RECENTLY MEASURED BY MACKLIN ET AL./2/  FOR RESO- 
    NANCES WHOSE NEUTRON WIDTH WAS NOT MEASURED, THE NEUTRON WIDTH
    WAS OBTAINED FROM THE CAPTURE AREA ASSUMING THE RADIATION     
    WIDTH OF 0.074 EV AND 0.089 EV FOR THE S-WAVE AND P-WAVE RESO-
    NANCES, RESPECTIVELY.  FOR P-WAVE RESONANCES, THE VALUE OF THE
    TOTAL SPIN J WAS ARBITRARILY ASSIGNED WITH THE RATIO 1:2 IN   
    THE NUMBER OF THE RESONANCES WITH J=1/2 AND J=3/2.  TO REPRO- 
    DUCE THE THERMAL CROSS SECTION OF 1.64+-0.10 B AT 0.0253      
    EV/3/, A NEGATIVE RESONANCE WAS ADDED AT 104 EV.  THE EFFEC-  
    TIVE SCATTERING RADIUS WAS EMPLOYED FROM THE MEASURED DATA BY 
    MACKLIN ET AL./2/                                             
                                                                  
  UNRESOLVED RESONANCE REGION : 30 EV - 100 KEV                   
    THE NEUTRON STRENGTH FUNCTION S0 WAS BASED ON THE COMPILATION 
    OF MUGHABGHAB/4/, AND S1 AND S2 WERE CALCULATED WITH OPTICAL  
    MODEL CODE CASTHY/5/.  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 = 3.200E-4, S1 = 1.900E-4, S2 = 2.000E-4, SG = 1.27E-4,    
    GG = 0.060 EV, R  = 5.748 FM.                                 
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL           2.3992                   -                  
      ELASTIC         0.7588                   -                  
      CAPTURE         1.6404                   1.91               
                                                                  
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/6/ 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 SECTIONS OF NATURAL SM  
  MEASURED BY FOSTER AND GLASGOW/7/, KELLIE ET AL./8/ AND SO      
  ON.  THE OMP'S FOR CHARGED PARTICLES ARE AS FOLLOWS:            
     PROTON   = PEREY/9/                                          
     ALPHA    = HUIZENGA AND IGO/10/                              
     DEUTERON = LOHR AND HAEBERLI/11/                             
     HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/12/            
  PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GILBERT   
  AND CAMERON/13/ WERE EVALUATED BY IIJIMA ET AL./14/  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
  /15/.                                                           
                                                                  
  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)/16/ AND NUCLEAR DATA       
    SHEETS/17/.                                                   
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY    DWUCK CAL       
           GR.       0.0             0  +                         
            1        1.6602          2  +             *           
            2        1.8101          3  -             *           
            3        2.1906          4  +                         
            4        2.3232          6  +                         
            5        2.4233          2  +                         
            6        2.4779          0  +                         
            7        2.5880          4  +                         
            8        2.8000          2  +                         
            9        2.8840          4  +                         
           10        3.0210          4  +                         
           11        3.1238          7  -                         
           12        3.1980          4  -                         
           13        3.2280          3  -                         
           14        3.2550          1  -                         
           15        3.3080          6  +                         
           16        3.3100          6  +                         
           17        3.3620          4  -                         
           18        3.3761          8  +                         
           19        3.3930          3  -                         
           20        3.4050          3  -                         
           21        3.4605          9  -                         
           22        3.5300          3  -                         
           23        3.6501          8  +                         
           24        3.6710          5  -                         
           25        3.7340          3  -                         
           26        3.8490          4  -                         
           27        3.8530          9  -                         
           28        3.8591          8  +                         
           29        3.8690          5  -                         
      LEVELS ABOVE 3.869 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 = 0.088 AND  
    BETA3 = 0.135) 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 (1.128E-4) WAS ADJUSTED TO    
    REPRODUCE THE CAPTURE CROSS SECTION OF 57 MILLI-BARNS AT 90   
    KEV MEASURED BY MACKLIN ET AL./2/                             
                                                                  
  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 =106  (N,HE3) CROSS SECTION                                  
  MT =107  (N,ALPHA) CROSS SECTION                                
  MT =111  (N,2P) CROSS SECTION                                   
    THESE REACTION CROSS SECTIONS WERE CALCULATED WITH THE        
    PREEQUILIBRIUM AND MULTI-STEP EVAPORATION MODEL CODE PEGASUS. 
                                                                  
    THE KALBACH'S CONSTANT K (= 158.4) WAS ESTIMATED BY THE       
    FORMULA DERIVED FROM KIKUCHI-KAWAI'S FORMALISM/22/ AND LEVEL  
    DENSITY PARAMETERS.                                           
                                                                  
    FINALLY, THE (N,P) AND (N,ALPHA) CROSS SECTIONS WERE          
    NORMALIZED TO THE FOLLOWING VALUES AT 14.5 MEV:               
      (N,P)         24.00  MB (RECOMMENDED BY FORREST/23/)        
      (N,ALPHA)     10.20  MB (SYSTEMATICS OF FORREST/23/)        
                                                                  
  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.  CONTRIBUTION OF DIRECT INELASTIC       
  SCATTERING WAS CALCULATED WITH DWUCK-4.  FOR OTHER REACTIONS,   
  ISOTROPIC DISTRIBUTIONS 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 = 6.237    A0 = 0.655        
        WS = 8.455                RS = 7.548    AS = 0.448        
        VSO= 7.0                  RSO= 6.709    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-140  *  1.641E+01 5.532E-01 2.596E-01 5.024E+00 1.880E+00  
 60-ND-141     1.477E+01 6.091E-01 9.537E-01 4.587E+00 1.180E+00  
 60-ND-142     1.288E+01 6.710E-01 2.250E-01 5.526E+00 2.030E+00  
 60-ND-143     1.826E+01 4.710E-01 5.220E-01 3.613E+00 1.180E+00  
                                                                  
 61-PM-141  *  1.653E+01 5.508E-01 2.224E+00 3.845E+00 7.000E-01  
 61-PM-142  *  1.619E+01 5.484E-01 6.721E+00 2.997E+00 0.0        
 61-PM-143  *  1.430E+01 5.459E-01 6.683E-01 3.187E+00 8.500E-01  
 61-PM-144     1.831E+01 5.100E-01 1.011E+01 3.040E+00 0.0        
                                                                  
 62-SM-142  *  1.665E+01 5.484E-01 2.438E-01 5.066E+00 1.920E+00  
 62-SM-143     1.628E+01 5.431E-01 6.981E-01 4.167E+00 1.220E+00  
 62-SM-144     1.557E+01 5.543E-01 1.323E-01 4.951E+00 2.070E+00  
 62-SM-145     2.045E+01 4.343E-01 5.095E-01 3.596E+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 15.12 FOR SM-144 AND 5.0 FOR SM-145.               
                                                                  
REFERENCES                                                        
 1) KAWAI, M. ET AL.: J. NUCL. SCI. TECHNOL., 29, 195 (1992).     
 2) MACKLIN, R.L. ET AL.: PHYS. REV., C48, 1120 (1993).           
 3) ALEXANDER, C.W. ET AL.: NUCL. SCI. ENG., 95, 194 (1987).      
 4) MUGHABGHAB, S.F.: "NEUTRON CROSS SECTIONS, VOL. I, PART B",   
    ACADEMIC PRESS (1984).                                        
 5) IGARASI, S. AND FUKAFORI, T.: JAERI 1321 (1991).              
 6) IIJIMA, S. ET AL.: JAERI-M 87-025, P. 337 (1987).             
 7) FOSTER, D.G. JR. AND GLASGOW, D.W.: PHYS. REV., C3, 576       
    (1971).                                                       
 8) KELLIE, J.D., HALL, S.J. AND CRAWFORD, G.I. ET AL.:           
    J. PHYS., A7, 1758 (1974).                                    
 9) PEREY, F.G: PHYS. REV. 131, 745 (1963).                       
10) HUIZENGA, J.R. AND IGO, G.: NUCL. PHYS. 29, 462 (1962).       
11) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).    
12) 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).                                                       
13) GILBERT, A. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446      
    (1965).                                                       
14) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).     
15) GRUPPELAAR, H.: ECN-13 (1977).                                
16) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE (JUNE 1987).     
17) NUCLEAR DATA SHEETS, 27,  97 (1979).                          
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) KIKUCHI, K. AND KAWAI, M.: "NUCLEAR MATTER AND NUCLEAR        
    REACTIONS", NORTH HOLLAND (1968).                             
23) FORREST, R.A.: AERE-R 12419 (1986).