63-Eu-153

 63-EU-153 JEARI,JNDC EVAL-MAR89 T.ASAMI, JNDC FP ND W.G.         
                      DIST-OCT89 REV2-JAN94                       
----JENDL-3.2         MATERIAL 6331                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
84-10 EVALUATION FOR JENDL-2 WAS MADE BY JNDC FPND W.G./1/        
89-03 EVALUATION FOR JENDL-3 WAS MADE BY T.ASAMI(JAERI) AND       
      JNDC FP NUCLEAR DATA W.G.                                   
90-02 A RESONANCE AT 0.457 EV WAS REMOVED.                        
       THIS MODIFICATION WAS MADE ONLY FOR MAT=6303.              
94-01 JENDL-3.2                                                   
      MODIFIED BY T.NAKAGAWA (NDC/JAERI)                          
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (2,151)         0.457-EV RESONANCE WAS DELETED.             
                          AFTER THIS MODIFICATION, THE DATA ARE   
                          THE SAME AS MAT=6303.                   
      (3,1)*          BELOE 2 EV, 83.95-100 KEV, AROUND 10 MEV.   
      (3,102)         Q-VALUE WAS CORRECTED.                      
      (3,107)*        BELOW 2 EV AND Q-VALUE CORRECTED.           
           *) MODIFICATION BELOW 2 EV WAS MADE ONLY TO MAT=3633   
     ***********************************************************  
                                                                  
                                                                  
MF = 1  GENERAL INFORMATION                                       
  MT=451 COMMENTS AND DICTIONARY                                  
                                                                  
MF = 2  RESONANCE PARAMETERS                                      
  MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS             
    EVALUATION WAS MADE BY KIKUCHI /2/.  NEUTRON WIDTHS WERE      
    OBTAINED BY AVERAGING THE DATA OF RAHN ET AL./3/ AND ANUFRIEV 
    ET AL./4/.  RADIATIVE CAPTURE WIDTHS WERE ADOPTED FROM THE    
    DATA MEASURED BY RAHN ET AL.  THE PARAMETERS OF 1.73-, 2.46-, 
    3.29- AND 3.94-EV LEVELS WERE TAKEN FROM MUGHABGHAB /5/ SO AS 
    TO REPRODUCE THE CAPTURE RESONANCE INTEGRAL OF 1420 +- 100    
    BARNS RECOMMENDED IN REF./5/.  A NEGATIVE RESONANCE WAS ADDED 
    AT -0.5 EV SO AS TO REPRODUCE THE CAPTURE CROSS SECTION OF 390
    +- 20 BARNS AND THE ELASTIC SCATTERING OF 8.0 +- 0.2 BARNS AT 
    0.0253 EV /6/.                                                
  UNRESOLVED RESONANCE REGION : 0.0972 KEV - 100 KEV              
    INITIAL VALUES OF NEUTRON STRENGTH FUNCTIONS WERE THE SAME AS 
    JENDL-2 CALCULATED WITH OPTICAL AND STATISTIACL MODEL CODE    
    CASTHY/7/.  THEY WERE ADJUSTED TO THE CAPTURE CROSS SECTION   
    CALCULATED WITH CASTHY FOR JENDL-2 WHICH WAS IN GOOD AGREEMENT
    WITH EXPERIMENTAL DATA BY MACKLIN AND YOUNG/8/.  THE OBSERVED 
    LEVEL SPACING WAS DETERMINED TO REPRODUCE THE CAPTURE CROSS   
    SECTION AT 30 KEV. 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 = 2.602E-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         323.0                      -                  
      ELASTIC        10.33                     -                  
      CAPTURE       312.7                    1410                 
     (N,ALPHA)        7.1E-07                                     
                                                                  
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,   
    DETERMINED FROM THE DATA OF FOSTER AND GLASGOW/9/ FOR         
    NATURAL EU.                                                   
                                                                  
  MT = 2  ELASTIC SCATTERING                                      
    CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS).        
                                                                  
  MT = 4, 51 - 91  INELASTIC SCATTERING                           
    CALCULATED WITH THE CASTHY CODE/7/.  THE LEVEL SCHEME USED IN 
    THE CALCULATIONS WAS TAKEN FROM REF./10/                      
                                                                  
         NO   LEVEL ENERGY(MEV)   SPIN-PARITY                     
         G.S.     0.0                 5/2+                        
          1       0.0834              7/2+                        
          2       0.0974              5/2-                        
          3       0.1032              3/2+                        
          4       0.1516              7/2-                        
          5       0.1729              5/2+                        
          6       0.1931              9/2+                        
          7       0.2353              9/2-                        
          8       0.2697              7/2+                        
          9       0.3219             11/2-                        
         10       0.3251             11/2+                        
         11       0.3964              9/2+                        
        LEVELS ABOVE 0.400 MEV WERE ASSUMED TO BE OVERLAPPING.    
                                                                  
  MT = 102  CAPTURE                                               
    CALCULATION FOR JENDL-2 WITH CASTHY/7/ WAS ADOPTED.  THE      
    FOLLOWING POTENTIAL PARAMETERS WERE DETERMINED BY IIJIMA ET   
    AL. /11/ TO REPRODUCE A SYSTEMATIC TREND OF THE TOTAL CROSS   
    SECTION.                                                      
                                                                  
                DEPTH (MEV)       RADIUS(FM)    DIFFUSENESS(FM)   
         ----------------------   ------------  ---------------   
        V  = 49.61                R0 = 6.7926   A0 = 0.6          
        WS = 10.595               RS = 7.6483   AS = 0.45         
        WSO= 7.0                  RSO= 6.8461   ASO= 0.6          
                                                                  
    PARAMETERS FOR THE COMPOSITE LEVEL DENSITY FORMULA OF GIRBERT-
    CAMERON WERE EVALUATED AS FOLLOWS/12/.  THE COEFFICIENT OF    
    SPIN CUT-OFF PARAMETER C1 WAS TAKEN AS 0.146.  THE ENERGY     
    DEPENDENCE OF SPIN CUT-OFF PARAMETER IN THE ENERGY RANGE BELOW
    E-JOINT IS DUE TO GRUPPELAAR /13/.                            
                                   EU-153      EU-154             
                                 --------    --------             
          PAIRING ENERGY (MEV)      1.100       0.0               
          A (1/MEV)                27.860      22.670             
          SPIN CUT-OFF PARAM.      19.567      19.972             
          NUCLEAR TEMP.(MEV)        0.455       0.432             
          C (1/MEV)                13.410      16.440             
          E-JOINT (MEV)             5.399       2.784             
                                                                  
    THE GAMMA-RAY STRENGTH FUNCTION (= 809.E-4) WAS ADJUSTED TO   
    REPRODUCE THE EXPERIMENTAL CAPTURE CROSS SECTION OF 680 MILLI-
    BARNS AT 250 KEV MEASURED BY MACKLIN AND YOUNG/8/.  DIRECT    
    AND SEMI-DIRECT CAPTURE CROSS SECTIONS WERE ESTIMATED         
    ACCORDING TO THE PROCEDURE OF BENZI AND REFFO/14/ AND         
    NORMALIZED TO 1 MILLI-BARN AT 14 MEV.                         
                                                                  
  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/15/ 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/9/ FOR NATURAL EU.  THE LEVEL SCHEME DATA WERE TAKEN  
    FROM REF./10/.  THE CALCULATED (N,P) CROSS SECTION WAS        
    NORMALIZED AT 14.5 MEV TO AN AVERAGE VALUE OF THE EXPERIMENTAL
    DATA AROUND 14.5 MEV/16,17,18,19/.                            
                                                                  
    THE (N,ALPHA) CROSS SECTION IN THE RESONANCE REGION WAS       
    CALCULATED FROM RESONANCE PARAMETERS, BY ASSUMING A MEAN ALPHA
    WIDTH OF 2.0E-10 EV SO AS TO REPRODUCE THE THERMAL CROSS      
    SECTION/5/.  THE CROSS SECTION WAS AVERAGED IN SUITABLE       
    ENERGY INTERVALS.  ABOVE 97.2 EV, 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, ISOTROPIC      
  DISTRIBUTIONS IN THE LABORATORY SYSTEM WERE ASSUMED.            
                                                                  
MF = 5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                
  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE CALCULATED WITH 
  GNASH/15/.                                                      
                                                                  
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) AOKI, T. ET AL.: PROC. INT. CONF. ON NUCLEAR DATA FOR BASIC   
    AND APPLIED SCIENCE, SANTA FE., VOL. 2, P.1627 (1985).        
 2) KIKUCHI, Y. ET AL.: JAERI-M 86-030 (1986).                    
 3) RAHN, F., ET AL.: PHYS. REV., C6, 251 (1972).                 
 4) ANUFRIEV, V.A., ET AL.: SOV. AT. ENERGY, 46, 182 (1979).      
 5) MUGHABGHAB, S.F.: "NEUTRON CROSS SECTIONS, VOL. I, PART B",   
    ACADEMIC PRESS (1984).                                        
 6) MUGHABGHAB, S.F. AND GARBER, D.I.: "NEUTRON CROSS SECTIONS,   
    VOL.1, RESONANCE PARAMETERS", BNL 325, 3RD ED., VOL. 1,       
    (1973).                                                       
 7) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).              
 8) MACKLIN, R.L. AND YOUNG, P.G.: NUCL. SCI. ENG., 95, 189(1987).
 9) FOSTER JR.D.G. AND GLASGOW D.W.: PHYS. REV., C3, 576 (1971).  
10) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE (JUNE 1987).     
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    (1983).                                                       
12) IIJIMA, S., ET AL.: J. NUCL. SCI. TECHNOL. 21, 10 (1984).     
13) GRUPPELAAR, H.: ECN-13 (1977).                                
14) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
15) YOUNG, P.G. AND ARTHUR, E.D.: LA-6947 (1977).                 
16) COLEMAN, R.F. ET AL.: PROC. PHYS. SOC., 73, 215 (1959).       
17) QAIM, S.M.: DATA IN THE EXFOR FILE (1974).                    
18) PRUYS, H.S. ET AL.: J. INORG. NUCL. CHEM., 37, 1587 (1975).   
19) BARI, A.: J. RADIOANAL. CHEM., 75, 189 (1982).