58-Ce-142

 58-CE-142 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 5843                               
-----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/.                       
93-09 JENDL-3.2 WAS MADE BY JNDC FPND W.G.                        
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (2,151)       UNRESOLVED RESONANCE PARAMETERS RE-ADJUSTED   
                    SO AS TO REPRODUCE THE RE-NORMALIZED CAPTURE  
                    CROSS SECTION.                                
      (3,102)       RE-NORMALIZATION.                             
      (3,2), (3,4), (3,51-91) AND ANGULAR DISTRIBUTIONS           
                    SMALL EFFECTS OF THE RE-NORMALIZATION OF      
                    CAPTURE CROSS SECTION.                        
     ***********************************************************  
                                                                  
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 26 KEV         
      RESONANCE PARAMETERS FOR JENDL-3 WERE EVALUATED BY TAKING   
    INTO ACCOUNT THE EXPERIMENTAL DATA BY OHKUBO ET AL./3/ IN     
    WHICH REDUCED NEUTRON WIDTHS WERE GIVEN IN THE ENERGY RANGE   
    FROM 1.277 TO 54.9 KEV.  THE UPPER BOUNDARY OF RESOLVED       
    RESONANCE REGION WAS DETERMINED TO BE 26 KEV AS A RESULT OF   
    STAIR-CASE PLOTTING.                                          
      AVERAGE RADIATION WIDTH OF 0.08 EV WAS ESTIMATED FROM FIG. 9
    IN REF./4/ AND THE SYSTEMATICS CURVE BY BENZI AND REFFO/5/.   
    SCATTERING RADIUS OF 5.9 FM WAS ADOPTED FROM THE COMPILATION  
    BY MUGHABGHAB ET AL./4/                                       
      NEUTRON ORBITAL ANGULAR MOMENTUM L OF SOME RESONANCES WAS   
    ESTIMATED WITH A METHOD OF BOLLINGER AND THOMAS/6/.           
      A NEGATIVE RESONANCE WAS ADDED SO AS TO REPRODUCE THE       
    THERMAL CAPTURE CROSS SECTION OF 0.95+-0.05 BARN RECOMMENDED  
    BY MUGHABGHAB ET AL.                                          
                                                                  
  UNRESOLVED RESONANCE REGION : 26 KEV - 100 KEV                  
    THE NEUTRON STRENGTH FUNCTION S0 WAS BASED ON THE COMPILATION 
    OF MUGHABGHAB ET AL., AND S1 AND S2 WERE CALCULATED WITH      
    OPTICAL MODEL CODE CASTHY/7/.  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 = 1.200E-4, S1 = 0.700E-4, S2 = 0.600E-4, SG = 0.233E-4,   
    GG = 0.070 EV, R  = 4.537 FM.                                 
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL           1.618                    -                  
      ELASTIC         0.6145                   -                  
      CAPTURE         1.004                     0.933             
                                                                  
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/8/ STANDING ON A PREEQUILIBRIUM AND MULTI-STEP     
  EVAPORATION MODEL.  THE OMP'S FOR NEUTRON GIVEN IN TABLE 1 WHICH
  WERE DETERMINED SO AS TO REPRODUCE THE LA-139 TOTAL CROSS       
  SECTION MEASURED BY FOSTER AND GLASGOW/9/, ISLAM ET AL./10/,    
  NISHIMURA ET AL./11/ AND SO ON WERE ADOPTED BY ASSUMING THAT THE
  TOTAL CROSS SECTION OF CE WAS SIMILER TO THAT OF LA-139.  THE   
  OMP'S FOR CHARGED PARTICLES ARE AS FOLLOWS:                     
     PROTON   = PEREY/12/                                         
     ALPHA    = HUIZENGA AND IGO/13/                              
     DEUTERON = LOHR AND HAEBERLI/14/                             
     HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/15/            
  PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GILBERT   
  AND CAMERON/16/ WERE EVALUATED BY IIJIMA ET AL./17/  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
  /18/.                                                           
                                                                  
  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./19/.           
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY    DWBA CAL.       
           GR.       0.0             0  +                         
            1        0.6412          2  +             *           
            2        1.2193          4  +                         
            3        1.5361          2  +                         
            4        1.6526          3  -             *           
            5        2.0042          2  +                         
            6        2.0300          0  +                         
            7        2.1870          1  +                         
            8        2.3640          1  +                         
            9        2.3980          1  +                         
      LEVELS ABOVE 2.5 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/20/.  DEFORMATION PARAMETERS (BETA2 = 0.1236 AND 
    BETA3 = 0.132) WERE BASED ON THE DATA COMPILED BY RAMAN ET    
    AL./21/ AND SPEAR/22/, 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/5/ AND NORMALIZED TO 1 MILLI-BARN AT 14 MEV.        
                                                                  
    THE GAMMA-RAY STRENGTH FUNCTION (2.06E-05) WAS DETERMINED SO A
    TO REPRODUCE THE CAPTURE CROSS SECTION OF 19+-4 MB AT 25 KEV  
    MEASURED BY R.P. ANAND ET AL./23/                             
                                                                  
  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 =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 (= 100.0) WAS DETERMINED TO REPRODUCE
    ENERGY DEPENDENCE OF THE (N,2N) CROSS SECTION MEASURED BY     
    TENG DAN ET AL./24/.                                          
                                                                  
    FINALLY, THE (N,P) AND (N,ALPHA) CROSS SECTIONS WERE          
    NORMALIZED TO THE FOLLOWING VALUES AT 14.5 MEV:               
      (N,P)          4.80  MB (RECOMMENDED BY FORREST/25/)        
      (N,ALPHA)      3.00  MB (RECOMMENDED BY FORREST)            
    THE (N,2N) CROSS SECTION WAS MODIFIED BY EYE-GUIDING OF THE   
    DATA MEASURED BY TENG DAN ET AL./24/  THE (N,3N) CROSS SECTION
    WAS DETERMINED BY SUBTRACTING THE (N,2N) CROSS SECTION FROM   
    THE SUM OF (N,2N) AND (N,3N) CROSS SECTIONS CALCULATED WITH   
    PEGASUS.                                                      
                                                                  
  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  = 41.8                 R0 = 6.923    A0 = 0.62         
        WS = 2.95+0.789E          RS = 7.132    AS = 0.35         
        VSO= 7.0                  RSO= 6.923    ASO= 0.62         
  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    
 ---------------------------------------------------------------  
 56-BA-138     1.390E+01 7.200E-01 4.123E-01 7.233E+00 2.430E+00  
 56-BA-139     2.022E+01 4.800E-01 5.326E-01 4.629E+00 1.580E+00  
 56-BA-140     1.500E+01 6.930E-01 5.738E-01 7.244E+00 2.340E+00  
 56-BA-141     1.600E+01 7.010E-01 3.318E+00 7.141E+00 1.580E+00  
                                                                  
 57-LA-139     1.380E+01 6.500E-01 1.653E+00 4.468E+00 8.500E-01  
 57-LA-140     1.558E+01 5.900E-01 7.912E+00 3.425E+00 0.0        
 57-LA-141     1.894E+01 5.130E-01 3.056E+00 4.024E+00 7.600E-01  
 57-LA-142     2.026E+01 4.610E-01 1.125E+01 2.749E+00 0.0        
                                                                  
 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  
 ---------------------------------------------------------------  
                                                                  
 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 3.236 FOR CE-142 AND 5.0 FOR CE-143.               
                                                                  
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) OHKUBO, M. ET AL.: PROC. INT. CONF. ON NUCLEAR DATA FOR       
    BASIC AND APPLIED SCIENCE, SANTA-FE., VOL.2, P.1623 (1985).   
 4) MUGHABGHAB, S.F. ET AL.: "NEUTRON CROSS SECTIONS, VOL. I,     
    PART A", ACADEMIC PRESS (1981).                               
 5) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
 6) BOLLINGER, L.M. AND THOMAS, G.E.: PHYS. REV., 171,1293(1968). 
 7) IGARASI, S. AND FUKAHORI. JAERI 1321 (1991).                  
 8) IIJIMA, S. ET AL.: JAERI-M 87-025, P. 337 (1987).             
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    (1971).                                                       
10) ISLAM, E., HUSSAIN, M., AMEEN, N., ET AL.: NUCL. PHYS., A209, 
    189 (1973).                                                   
11) NISHIMURA, K., YAMANOUTI, Y., KIKUCHI, S., ET AL.:  EANDC(J)  
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    NISHIMURA, K. ET AL.: JAERI-M 6883 (1977).                    
12) PEREY, F.G: PHYS. REV. 131, 745 (1963).                       
13) HUIZENGA, J.R. AND IGO, G.: NUCL. PHYS. 29, 462 (1962).       
14) LOHR, J.M. AND HAEBERLI, W.: NUCL. PHYS. A232, 381 (1974).    
15) 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).                                                       
16) GILBERT, A. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446      
    (1965).                                                       
17) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).     
18) GRUPPELAAR, H.: ECN-13 (1977).                                
19) LEDERER, C.M., ET AL.: "TABLE OF ISOTOPES, 7TH ED.", WILEY-   
    INTERSCIENCE PUBLICATION (1978).                              
20) KUNZ, P.D.: PRIVATE COMMUNICATION.                            
21) RAMAN, S., ET AL.: ATOM. DATA AND NUCL. DATA TABLES 36, 1     
    (1987)                                                        
22) SPEAR, R.H.: ATOM. DATA AND NUCL. DATA TABLE, 42, 55 (1989).  
23) ANAND, R.P. ET AL.: NUOVO CIMENTO, A50, 274 (1979).           
    EXFOR 30390014.                                               
24) TENG DAN, ET AL.: CHINESE J. OF NUCL. PHYS., 7, 307 (1985)    
25) FORREST, R.A.: AERE-R 12419 (1986).