95-Am-244

 95-AM-244 JAERI      EVAL-MAR88 T.NAKAGAWA                       
JAERI-M 89-008        DIST-MAR02 REV2-FEB02            20020222   
----JENDL-3.3         MATERIAL 9552                               
-----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                                                           
88-03 EVALUATED FOR JENDL-3 WAS MADE BY T.NAKAGAWA (JAERI)/1/.    
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451   COMMENT AND DICTIONARY                                 
  MT=452   NUMBER OF NEUTRONS PER FISSION                         
        SUM OF NU-P (MT=456) AND NU-D (MT=455).                   
  MT=455   DELAYED NEUTRON DATA                                   
        ESTIMATED FROM SEMI-EMPIRICAL FORMULA BY TUTTLE /2/.      
  MT=456   NUMBER OF PROMPT NEUTRONS                              
        ESTIMATED FROM SEMI-EMPIRICAL FORMULA BY HOWERTON/3/.     
                                                                  
MF=2,MT=151   RESONANCE PARAMETERS                                
  NO RESONANCE PARAMETERS WERE GIVEN.                             
                                                                  
  2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS                 
                      2200 M/S VALUE       RES. INT.              
        TOTAL          2912.  B              -                    
        ELASTIC         11.62 B              -                    
        FISSION        2300.  B             1260  B               
        CAPTURE         600.  B              316  B               
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  MT=1  TOTAL CROSS SECTION                                       
        BELOW 0.07 EV, SUM OF PARTIAL CROSS SECTIONS.  ABOVE 0.07 
        EV, CALCULATED WITH OPTICAL AND STATISTICAL MODEL CODE    
        CASTHY/4/. THE SAME OPTICAL POTENTIAL PARAMETERS AS THOSE 
        FOR AM-242 WHICH WERE OBTAINED /5/ BY FITTING THE DATA OF 
        PHILLIPS AND HOWE /6/ FOR AM-241, AND MODIFIED A LITTLE.  
           V = 42.0 - 0.107*EN                      (MEV)         
           WS= 9.0  - 0.339*EN + 0.0531*EN**2       (MEV)         
           VSO = 7.0                                (MEV)         
           R = RSO = 1.282   , RS = 1.29            (FM)          
           A = ASO = 0.60    , B  = 0.5             (FM)          
                                                                  
  MT=2  ELASTIC SCATTERING CROSS SECTION                          
        CALCULATED WITH CASTHY/4/.                                
                                                                  
  MT=4,51-75,91  INELASTIC SCATTERING CROSS SECTIONS              
        CALCULATED WITH CASTHY/4/.  THE LEVEL SCHEME WAS TAKEN    
        FROM REF. /7/                                             
                   NO         ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0           6 -                
                    1             88.0         1 +                
                    2            100.309       2 +                
                    3            123.281       3 +                
                    4            148.283       4 +                
                    5            175.657       1 -                
                    6            183.511       5 -                
                    7            197.295       2 -                
                    8            228.299       3 -                
                    9            261.696       2 -                
                   10            272.202       4 -                
                   11            289.212       1 -                
                   12            296.658       3 -                
                   13            322.751       5 -                
                   14            355.575       0 -                
                   15            342.650       3 -                
                   16            343.658       4 -                
                   17            348.405       3 +                
                   18            361.838       2 -                
                   19            377.057       0 +                
                   20            390.028       4 +                
                   21            398.743       5 -                
                   22            414.689       2 +                
                   23            418.957       2 +                
                   24            420.131       2 +                
                   25            421.204       3 -                
            LEVELS ABOVE 435 KEV WERE ASSUMED TO BE OVERLAPPING.  
        THE LEVEL DENSITY PARAMETERS WERE DETERMINED ON THE BASIS 
        OF NUMBER OF EXCITED LEVELS/8/ AND RESONANCE LEVEL        
        SPACING/9/.                                               
                                 AM-245     AM-244                
                      A(1/MEV)    31.3       30.3                 
                        T(MEV)    0.360      0.340                
                      C(1/MEV)    18.06      26.47                
                      E-X(MEV)    3.265      2.373                
       SPIN-CUTOFF(1/MEV**0.5)    31.98      31.39                
                PAIRING E(MEV)    0.39       0.0                  
                                                                  
  MT=16,17,37  (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS  
        CALCULATED WITH EVAPORATION MODEL.                        
                                                                  
  MT=18  FISSION CROSS SECTION                                    
        BELOW 0.07 EV, 1/V SHAPED CROSS SECTION WAS NORMALIZED TO 
        2300 +- 300 B AT 0.0253 EV/9/.  ABOVE 0.07 EV, THE CROSS  
        SECTION WAS ASSUMED TO BE THE SAME AS THAT OF AM-242G     
        (MAT=3952 OF JENDL-3).                                    
                                                                  
  MT=102 CAPTURE CROSS SECTION                                    
        BELOW 0.07 EV, 1/V CROSS SECTION WAS NORMALIZED TO 600 B  
        AT 0.0253 EV THAT WAS ESTIMATED BY ASSUMING THE SAME CROSS
        SECTION RATIO AS HIGHER ENERGY REGION.  ABOVE 0.07 EV,    
        CALCULATED WITH CASTHY/4/.  THE GAMMA-RAY STRENGTH        
        FUNCTION WAS DETERMINED FROM D-OBS=0.13 EV CALCULATED FROM
        LEVEL DENSITY PARAMETERS AND WG=0.05 EV.                  
                                                                  
  MT=251 MU-L BAR                                                 
        CALCULATED WITH CASTHY/4/.                                
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-75,91                                                   
          LEGENDRE COEFFICIENTS WERE GIVEN BY THE OPTICAL AND     
          STATISTICAL MODEL CALCULATION.                          
  MT=16,17,18,37                                                  
          ISOTROPIC DISTRIBUTIONS IN THE LABORATORY SYSTEM.       
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,37,91                                                  
          EVAPORATION SPECTRUM WITH NUCLEAR TEMPERATURE CALCULATED
          FROM LEVEL DENSITIES.                                   
  MT=18                                                           
          MAXWELLIAN FISSION SPECTRUM ESTIMATED FROM Z**2/A       
          SYSTEMATICS BY SMITH ET AL./10/.                        
                                                                  
REFERENCES                                                        
 1) NAKAGAWA T.: JAERI-M 89-008 (1989).                           
 2) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL , P.29 (1979).           
 3) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).               
 4) IGARASI S.: J. NUCL. SCI. TECHNOL., 12, 67 (1975).            
 5) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).              
 6) PHILLIPS T.W. AND HOWE R.E.: NUCL. SCI. ENG., 69, 375 (1979). 
 7) SHURSHIKOV E.N.: NUCL. DATA SHEETS, 49, 785 (1986).           
 8) ENSDF, EVALUATED NUCLEAR STRUCTURE DATA FILE (1988).          
 9) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL. 1, PART B",    
    ACADEMIC PRESS, INC. (1984).                                  
10) SMITH A.B.: ANL/NDM-50 (1979).