63-Eu- 0

 63-EU-  0 JAERI,JNDC EVAL-MAR89 T.ASAMI, JNDC FP ND W.G.         
                      DIST-OCT89 REV2-NOV93                       
----JENDL-3.2         MATERIAL 6300                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
89-03 EVALUATION FOR EACH ISOTOPE WAS MADE BY T.ASAMI(JAERI) AND  
      JNDC FP NUCLEAR DATA W.G.  DATA FOR NATURAL EU WERE         
      CONSTRUCTED FROM THE ISOTOPE DATA BY T.ASAMI AND            
      T.NAKAGAWA(JAERI).                                          
90-06 (MF3,MT251) MODIFIED.                                       
93-11 JENDL-3.2                                                   
      GAMMA-RAY PRODUCTION DATA RE-EVALUATED BY T.ASAMI(DATA ENG.)
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (2,151)         SMALL MODIFICATION OF EU-153 PARAMETERS.    
      (3,102)         Q-VALUES WERE CAHNGED.                      
      (12,102)        BELOW 21.64 KEV                             
      (15,102)        BELOW 21.64 KEV                             
     ***********************************************************  
                                                                  
                                                                  
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)                        
    EVALUATION FOR EACH ISOTOPE WAS MADE BY KIKUCHI /1/.          
    1) EU-151: BELOW 98.2 EV                                      
       PARAMETERS WERE MAINLY BASED ON THE DATA OF RAHN ET AL.    
       /2/, AND FOR THE LOWEST 2 LEVELS, THE DATA OF TASSAN ET    
       AL./3/.  THE CAPTURE WIDTH OF 0.093 EV /2/ WAS ASSUMED FOR 
       THE LEVELS WHOSE RADIATIVE CAPTURE WIDTH WAS NOT MEASURED. 
       A NEGATIVE RESONANCE WAS ADDED SO AS TO REPRODUCE THE      
       CAPTURE CROSS SECTION OF 9200 BARNS AT 0.0253 EV/4/.       
    2) EU-153: BELOW 97.2 EV                                      
       NEUTRON WIDTHS WERE OBTAINED FROM THE DATA OF RAHN ET AL.  
       /2/ AND ANUFRIEV ET AL./5/.  RADIATIVE CAPTURE WIDTHS WERE 
       ADOPTED FROM THE DATA OF RAHN ET AL.  THE PARAMETERS OF    
       1.73-, 2.46-, 3.29- AND 3.94-EV LEVELS WERE TAKEN FROM     
       MAGHABGHAB /6/ SO AS TO REPRODUCE THE CAPTURE RESONANCE    
       INTEGRAL OF 1420 BARNS/6/.  A NEGATIVE RESONANCE WAS ADDED 
       SO AS TO REPRODUCE THE CAPTURE CROSS SECTION OF 390 BARNS  
       AND THE ELASTIC SCATTERING OF 8.0 +- 0.2 BARNS AT 0.0253   
       EV/4/.                                                     
  UNRESOLVED RESONANCE REGION : UP TO 100 KEV                     
    THE PARAMETERS WERE ADJUSTED TO REPRODUCE THE CAPTURE CROSS   
    SECTIONS.  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:                     
   1) EU-151                                                      
      S0 = 3.699E-4, S1 = 0.100E-4, S2 = 3.000E-4, GG = 0.091 EV  
      DO = 0.408 EV, R  = 6.870 FM.                               
   2) EU-153                                                      
      S0 = 2.602E-4, S1 = 1.394E-4, S2 = 2.946E-4, GG = 0.094 EV  
      DO = 1.489 EV, R  = 6.421 FM.                               
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS (BARNS)   
                     2200 M/S               RES. INTEG.           
      TOTAL          4566.6                    -                  
      ELASTIC         6.925                    -                  
      CAPTURE        4559.7                  2202                 
     (N,ALPHA)        4.637E-06                                   
                                                                  
MF = 3  NEUTRON CROSS SECTIONS                                    
  BELOW 100 KEV, RESONANCE PARAMETERS WERE GIVEN.                 
                                                                  
  MT = 1  TOTAL                                                   
    BELOW 10 MEV, CALCULATED WITH THE CASTHY CODE/7/. THE OPTICAL 
    POTENTIAL PARAMETERS LISTED IN TABLE 1 USED.  ABOVE 10 MEV,   
    CROSS SECTION WAS DETERMINED FROM THE DATA OF FOSTER AND      
    GLASGOW/8/ FOR NATURAL EU.                                    
                                                                  
  MT = 2  ELASTIC SCATTERING                                      
    CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS).        
                                                                  
  MT = 4, 51-71, 91  INELASTIC SCATTERING                         
    CALCULATED WITH THE CASTHY CODE/7/.  THE LEVEL SCHEME USED IN 
    THE CALCULATIONS WAS TAKEN FROM REF./9/                       
                                                                  
              EU-151                        EU-153                
      NO  MT  ENERGY(MEV) J-PARITY   NO. MT  ENERGY(MEV) J-PARITY 
     G.S      0.0         5/2+      G.S      0.0         5/2+     
       1  51  0.02150     7/2+        1  52  0.0834      7/2+     
       2  58  0.19620    11/2-        2  53  0.0974      5/2-     
       3  59  0.19650     3/2+        3  54  0.1032      3/2+     
       4  61  0.2432      7/2-        4  55  0.1516      7/2-     
       5  62  0.2604      5/2+        5  56  0.1729      5/2+     
       6  64  0.3070      7/2+        6  57  0.1931      9/2+     
       7  65  0.3075      5/2+        7  60  0.2353      9/2-     
       8  68  0.3498      9/2-        8  63  0.2697      7/2+     
       9  69  0.3536      7/2-        9  66  0.3219     11/2-     
      10  71  0.4160      7/2+       10  67  0.3251     11/2+     
                                     11  70  0.3964      9/2+     
    CONT  91  0.420                CONT  91  0.400                
                                                                  
       Q-VALUES OF EXCITED LEVELS WERE SHIFTED A LITTLE SO        
       AS TO BE CONSISTENT WITH THRESHOLD ENERGIES.               
                                                                  
  MT = 102  CAPTURE                                               
    CALCULATED FROM EU-151 AND -153 CAPTURE CROSS SECTIONS.       
    THE EU-151 CAPTURE CROSS SECTION BELOW 2 MEV WAS DETERMINED BY
    EYE-GUIDING THE DATA MEASURED BY MACKLIN AND YOUNG/10/, AND   
    ABOVE 2 MEV, JENDL-2 DATA CALCULATED WITH CASTHY WAS          
    NORMALIZED TO MACKLIN AND YOUNG AT 2 MEV.  FOR EU-153,        
    EVALUATION FOR JENDL-2 WAS ADOPTED.  DIRECT AND SEMI-DIRECT   
    CAPTURE CROSS SECTIONS WERE ADDED, WHICH WERE ESTIMATED       
    ACCORDING TO THE PROCEDURE OF BENZI AND REFFO/11/ AND         
    NORMALIZED TO 1 MILLI-BARN AT 14 MEV.                         
                                                                  
    Q-VALUE WAS DETERMINED BY WEIGHTED AVERAGE.                   
                                                                  
  MT=16, 17, 22, 28, 103, 107  (N,2N), (N,3N), (N,NA), (N,NP),    
     (N,P) AND (N,A) CROSS SECTIONS                               
    CALCULATED WITH THE GNASH CODE/12/ USING THE OPTICAL MODEL    
    PARAMETERS IN TABLE 2, WHICH WERE DETERMINED SO AS TO         
    REPRODUCE WELL THE TOTAL CROSS SECTION MEASURED BY FOSTER AND 
    GLASGOW/8/ FOR NATURAL EU.  THE LEVEL SCHEME DATA WERE TAKEN  
    FROM REF./9/.  THE CALCULATED (N,2N) AND (N,3N) CROSS SECTIONS
    WERE MODIFIED ON THE BASIS OF THE EXPERIMENTAL DATA OF FREHAUT
    ET AL./13/ AND BAYHURT/14/, RESPECTIVELY.                     
                                                                  
    THE (N,ALPHA) CROSS SECTION IN THE RESONANCE REGION WAS       
    CALCULATED FROM RESONANCE PARAMETERS, BY ASSUMING A MEAN ALPHA
    WIDTH OF 9.0E-11 EV FOR EU-151 AND 2.0E-10 EV FOR EU-153 SO AS
    TO REPRODUCE THE THERMAL CROSS SECTION/6/.  THE CROSS SECTION 
    WAS AVERAGED IN SUITABLE ENERGY INTERVALS.  ABOVE THE RESOLVED
    RESONANCE REGION, THE CROSS SECTION WAS CONNECTED SMOOTHLY TO 
    THE GNASH CALCULATION.                                        
                                                                  
  MT = 251  MU-BAR                                                
    CALCULATED WITH CASTHY/7/.                                    
                                                                  
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/7/.  FOR OTHER REACTIONS, THE ISOTROPIC  
  DISTRIBUTIONS IN THE LABORATORY SYSTEM WERE ASSUMED.            
                                                                  
MF = 5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                
  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE CALCULATED WITH 
  GNASH/12/.                                                      
                                                                  
MF = 12  PHOTON PRODUCTION MULTIPLICITIES                         
 MT=102 (BELOW 21.6437 KEV)                                       
    CALCULUATED FROM ENERGY BALANCE.                              
 MT=107 (BELOW 21.6437 KEV)                                       
    CALCULUATED WITH GNASH CODE/12/.                              
                                                                  
MF = 13 PHOTON PRODUCTION CROSS SECTIONS                          
 MT=3 (ABOVE 21.6437 KEV)                                         
    CALCULUATED WITH GNASH CODE/12/.                              
                                                                  
MF = 14 PHOTON ANGULAR DISTRIBUTIONS                              
 MT=3, 102                                                        
    ASSUMED TO BE ISOTROPIC.                                      
                                                                  
MF = 15 CONTINUOUS PHOTON ENERGY SPECTRA                          
 MT=3, 102, 107                                                   
    CALCULATED WITH GNASH CODE/12/.  SPECTRA OF MT=102 AT 1.0E-5  
    EV AND 0.0253 EV WERE CALCULATED WITH CASTHY/7/.              
                                                                  
TABLE 1  NEUTRON OPTICAL POTENTIAL PARAMETERS (FOR CASTHY)        
                                                                  
         V  = 43.71 - 0.0566*EN,     VSO = 7.9   (MEV)            
         WS = 7.696,                  WV = 0.0   (MEV)            
          R = 1.270,  RS = 1.440,  RSO = 1.280   (FM)             
          A = 0.60,    B = 0.45,   ASO = 0.60    (FM)             
                                                                  
TABLE 2  NEUTRON OPTICAL POTENTIAL PARAMETERS (FOR GNASH)         
                                                                  
         V  = 43.71 - 0.05655*EN,    VSO = 0.0   (MEV)            
         WS = 7.696,                  WV = 0.0   (MEV)            
          R = 1.272,  RS = 1.440,  RSO = 1.270   (FM)             
          A = 0.48,    B = 0.45,   ASO = 0.48    (FM)             
                                                                  
REFERENCES                                                        
 1) KIKUCHI, Y. ET AL.: JAERI-M 86-030 (1986).                    
 2) RAHN, F., ET AL.: PHYS. REV., C6, 251 (1972).                 
 3) TASSAN, S., ET AL.: NUCL. SCI., ENG., 10, 169 (1961).         
 4) MUGHABGHAB, S.F., GARBER, D.I.: "NEUTRON CROSS SECTIONS,      
    VOL.1, RESONANCE PARAMETERS", BNL 325, 3RD ED., VOL. 1,       
    (1973).                                                       
 5) ANUFRIEV, V.A., ET AL.: SOV. AT. ENERGY, 46, 182 (1979).      
 6) MUGHABGHAB, S.F. ET AL.: "NEUTRON CROSS SECTIONS, VOL. I,     
    PART A", ACADEMIC PRESS (1981).                               
 7) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).              
 8) FOSTER JR.D.G. AND GLASGOW D.W.: PHYS. REV., C3, 576 (1971).  
 9) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE (JUNE 1987).     
10) MACKLIN, R.L. AND YOUNG, P.G.: NUCL. SCI. ENG., 95, 189(1987).
11) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
12) YOUNG, P.G. AND ARTHUR, E.D.: LA-6947 (1977).                 
13) FREHAUT, J. ET AL.: DATA (1980) IN THE EXFOR FILE.            
14) BAYHURST, B.P. ET AL.: PHYS. REV., C12, 451 (1975).