60-Nd-144

 60-ND-144 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 6031                               
-----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/.                       
93-10 JENDL-3.2 WAS MADE BY JNDC FPND W.G.                        
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (2,151)       RESOLVED RESONANCE PARAMETERS                 
     ***********************************************************  
                                                                  
                                                                  
MF = 1  GENERAL INFORMATION                                       
  MT=451 COMMENTS AND DICTIONARY                                  
                                                                  
MF = 2  RESONANCE PARAMETERS                                      
  MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS             
  RESOLVED RESONANCE PARAMETERS FOR MLBW FORMULA (BELOW 12 KEV)   
      RESONANCE PARAMETERS ADOPTED IN JENDL-3.1 WERE TAKEN FROM   
    JENDL-2/3/:  RESONANCE ENERGIES WERE TAKEN FROM TELLIER/4/    
    AND MUSGROVE ET AL./5/ BY ADJUSTING TO THOSE OF REF./4/.      
    NEUTRON WIDTHS WERE TAKEN FROM REF./4/, AND RADIATION WIDTHS  
    WERE DEDUCED FROM THE CAPTURE AREAS OF MUSGROVE ET AL.  FOR   
    THE RESONANCES NOT MEASURED BY TELLIER, NEUTRON WIDTHS WERE   
    ESTIMATED FROM THE CAPTURE AREAS BY ASSUMING THE AVERAGE      
    RADIATION WIDTHS OF 0.047 EV FOR S-WAVE RESONANCES AND OF     
    0.041 EV FOR P-WAVE ONES.  FOR THE LOWEST 2 LEVELS, THE       
    CAPTURE WIDTHS OF KARZHAVINA ET AL./6/ WERE ADOPTED.  A       
    NEGATIVE RESONANCE WAS ADDED AT -76 EV SO AS TO REPRODUCE THE 
    CAPTURE CROSS SECTION OF 3.8+-0.3 BARNS AT 0.0253 EV /7/.     
      FOR JENDL-3.2, THE CAPTURE DATA MEASURED AT ORELA OF ORNL   
    WERE RENORMALIZED (FACTOR = 0.967)/8/.  THE NEUTRON WIDTH     
    AND/OR THE RADIATION WIDTH WAS REVISED TO REPRODUCE THE       
    RENORMALIZED CAPTURE AREA FOR EACH RESONANCE ABOVE 2.6 KEV.   
    EFFECTIVE SCATTERING RADIUS RECOMMENDED IN REF./9/ WAS        
    ADOPTED AND PARAMETERS OF THE NAGATIVE LEVEL WERE ADJUSTED TO 
    THERMAL CROSS SECTIONS/9/.                                    
                                                                  
  UNRESOLVED RESONANCE REGION : 12 KEV - 100 KEV                  
    UNRESOLVED RESONANCE PARAMETERS WERE ADOPTED FROM JENDL-2.    
    THE NEUTRON STRENGTH FUNCTIONS, S0, S1 AND S2 WERE CALCULATED 
    WITH OPTICAL MODEL CODE CASTHY/10/.  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 = 2.928E-4, S1 = 0.688E-4, S2 = 3.543E-4, SG = 0.998E-4,   
    GG = 0.041 EV, R  = 7.660 FM.                                 
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL           4.6036                   -                  
      ELASTIC         1.0007                   -                  
      CAPTURE         3.6030                  4.30                
                                                                  
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/11/ STANDING ON A PREEQUILIBRIUM AND MULTI-STEP    
  EVAPORATION MODEL.  THE OMP'S FOR NEUTRON GIVEN IN TABLE 1 WERE 
  DETERMINED BY IIJIMA AND KAWAI/12/ TO REPRODUCE A SYSTEMATIC    
  TREND OF THE TOTAL CROSS SECTION.  THE OMP'S FOR CHARGED        
  PARTICLES ARE AS FOLLOWS:                                       
     PROTON   = PEREY/13/                                         
     ALPHA    = HUIZENGA AND IGO/14/                              
     DEUTERON = LOHR AND HAEBERLI/15/                             
     HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/16/            
  PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GILBERT   
  AND CAMERON/17/ WERE EVALUATED BY IIJIMA ET AL./18/  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
  /19/.                                                           
                                                                  
  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./20/.           
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY    DWBA CAL.       
           GR.       0.0             0  +                         
            1        0.6965          2  +             *           
            2        1.3147          4  +                         
            3        1.5106          3  -             *           
            4        1.5610          2  +                         
            5        1.7913          6  +                         
      LEVELS ABOVE 1.817 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/21/.  DEFORMATION PARAMETER (BETA2 = 0.1309) WAS 
    BASED ON THE DATA COMPILED BY RAMAN ET AL./22/ AND BETA3 =    
    0.143 WAS PRESENTLY DETERMINED.                               
                                                                  
  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/23/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.       
                                                                  
    THE GAMMA-RAY STRENGTH FUNCTION (9.12E-05) WAS ADJUSTED TO    
    REPRODUCE THE CAPTURE CROSS SECTION OF 70 MILLI-BARNS AT 30   
    KEV MEASURED BY MUSGROVE ET AL./24/ AND BY KONONOV ET AL.     
    /25/                                                          
                                                                  
  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./26/.                                           
                                                                  
    FINALLY, THE (N,P) AND (N,ALPHA) CROSS SECTIONS WERE          
    NORMALIZED TO THE FOLLOWING VALUES AT 14.5 MEV:               
      (N,P)         12.00  MB (RECOMMENDED BY FORREST/27/)        
      (N,ALPHA)       5.40 MB (AVERAGE OF DATA MEASURED BY        
                              GMUCA+/28/ AND QAIM/29/.            
                                                                  
  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 TO OVERLAPPING LEVELS AND FOR  
  OTHER NEUTRON EMITTING REACTIONS.                               
                                                                  
TABLE 1  NEUTRON OPTICAL POTENTIAL PARAMETERS                     
                                                                  
                DEPTH (MEV)       RADIUS(FM)    DIFFUSENESS(FM)   
         ----------------------   ------------  ---------------   
        V  = 47.94                R0 = 6.718    A0 = 0.6          
        WS = 9.13                 RS = 7.564    AS = 0.45         
        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       A(1/MEV)  T(MEV)    C(1/MEV)  EX(MEV)   PAIRING    
 ---------------------------------------------------------------  
 58-CE-140     1.413E+01 6.541E-01 3.376E-01 5.852E+00 2.020E+00  
 58-CE-141     1.714E+01 5.150E-01 7.134E-01 3.957E+00 1.170E+00  
 58-CE-142     1.600E+01 6.000E-01 4.210E-01 5.674E+00 1.930E+00  
 58-CE-143     1.900E+01 5.500E-01 2.613E+00 5.094E+00 1.170E+00  
                                                                  
 59-PR-141     1.400E+01 6.500E-01 1.810E+00 4.559E+00 8.500E-01  
 59-PR-142     1.595E+01 6.150E-01 1.201E+01 3.974E+00 0.0        
 59-PR-143     1.500E+01 6.280E-01 2.607E+00 4.558E+00 7.600E-01  
 59-PR-144     1.600E+01 6.000E-01 1.045E+01 3.744E+00 0.0        
                                                                  
 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  
 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  
 ---------------------------------------------------------------  
                                                                  
 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 8.725 FOR ND-144 AND 6.875 FOR ND-145.             
                                                                  
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    AND APPLIED SCIENCE, SANTA FE., VOL. 2, P.1627 (1985).        
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    (1983).                                                       
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    (1971).                                                       
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    (1965).                                                       
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19) GRUPPELAAR, H.: ECN-13 (1977).                                
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    INTERSCIENCE PUBLICATION (1978).                              
21) KUNZ, P.D.: PRIVATE COMMUNICATION.                            
22) RAMAN, S., ET AL.: ATOM. DATA AND NUCL. DATA TABLES 36, 1     
    (1987)                                                        
23) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
24) MUSGROVE, A.R. DE L., ET AL.: PROC. INT. CONF. ON NEUTRON     
    PHYSICS AND NUCL. DATA FOR REACTORS, HARWELL 1978, 449.       
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26) FREHAUT, J., ET AL.: SYMP. ON NEUTRON CROSS SECTIONS FROM     
    10-50MEV, BNL, P.399 (1980).                                  
27) FORREST, R.A.: AERE-R 12419 (1986).                           
28) GUMCA, S., ET AL.: ACTA PHYS. SOLVOCA, 33, 9 (1983).          
29) QAIM, S.M.: RADIOCHIMICA ACTA., 35, 9 (1984).