95-Am-241

 95-AM-241 JAERI      EVAL-MAR88 T.NAKAGAWA                       
JAERI-M 89-008        DIST-SEP89                                  
----JENDL-3.2         MATERIAL 9543                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
82-03 EVALUATION FOR JENDL-2 WAS MADE BY Y.KIKUCHI (JAERI) /1/.   
88-03 RE-EVALUATION FOR JENDL-3 WAS MADE BY T.NAKAGAWA (JAERI)    
      /2/.                                                        
                                                                  
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 WITH SEMI-EMPIRICAL FORMULA BY TUTTLE /3/.  
  MT=456   NUMBER OF PROMPT NEUTRONS                              
            EXPERIMENTAL DATA OF JAFFEY AND LERNER /4/.           
                                                                  
MF=2,MT=151   RESONANCE PARAMETERS                                
  RESOLVED RESONANCES FOR MLBW FORMULA : 1.0E-5 - 150 EV          
        DATA OF DERRIEN AND LUCAS /5/ WERE ADOPTED AND 5 NEGATIVE 
        RESONANCES WERE ADDED.  VALUES OF TOTAL SPIN J WERE       
        REPLACED WITH ARBITRARILY ASSUMED VALUES.                 
                                                                  
  UNRESOLVED RESONANCES : 150 EV - 30 KEV                         
        PARAMETERS WERE DETERMINED BY USING ASREP/6/ SO AS TO     
        REPRODUCE THE CAPTURE CROSS SECTION MEASURED BY VANPRAET  
        ET AL. /7/ AND THE FISSION CROSS SECTION BY DABBS ET AL.  
        /8/.                                                      
          ENERGY INDEPENDENT PARAMETERS:                          
            R=9.37 FM, GAM-G=0.044 EV,  DOBS=0.4 EV               
          ENERGY DEPENDENT PARAMETERS:                            
            AT 150 EV: S0= 1.08E-4, S1=2.72E-4, WF=0.24 MILLI-EV  
            AT 30 KEV: S0= 0.79E-4, S1=1.99E-4, WF=0.30 MILLI-EV  
                                                                  
  CALCULATED 2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS      
                      2200 M/S VALUE       RES. INT.              
        TOTAL           614.6   B            -                    
        ELASTIC          11.13  B            -                    
        FISSION           3.018 B           13.9  B               
        CAPTURE         600.4   B           1300  B               
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
                                                                  
  MT=1,2  TOTAL AND ELASTIC SCATTERING CROSS SECTIONS             
        CALCULATED WITH OPTICAL AND STATISTICAL MODELS BY USING   
        CASTHY/9/.  OPTICAL POTENTIAL PARAMETERS/10/ WERE OBTAINED
        BY FITTING THE DATA OF PHILLIPS AND HOWE /11/ :           
           V = 43.4 - 0.107*EN                      (MEV)         
           WS= 6.95 - 0.339*EN + 0.0531*EN**2       (MEV)         
           WV= 0             , VSO = 7.0            (MEV)         
           R = RSO = 1.282   , RS = 1.29            (FM)          
           A = ASO = 0.60    , B  = 0.5             (FM)          
                                                                  
  MT=4,51-66,91  INELASTIC SCATTERING CROSS SECTIONS              
        OPTICAL AND STATISTICAL MODEL CALCULATION WITH CASTHY CODE
        /9/.  THE LEVEL SCHEME WAS TAKEN FROM REF. /12/           
                   NO         ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0           5/2 -              
                    1             41.176       7/2 -              
                    2             93.65        9/2 -              
                    3            158.0        11/2 -              
                    4            205.883       5/2 +              
                    5            235.0         7/2 +              
                    6            272.0         9/2 +              
                    7            320.0        11/2 +              
                    8            471.81        3/2 -              
                    9            504.448       5/2 -              
                   10            549.0         7/2 -              
                   11            623.1         1/2 +              
                   12            636.861       3/2 -              
                   13            652.089       1/2 -              
                   14            653.23        3/2 +              
                   15            670.24        3/2 +              
                   16            682.0        11/2 -              
                CONTINUUM LEVELS ASSUMED ABOVE 732 KEV.           
        THE LEVEL DENSITY PARAMETERS WERE DETERMINED ON THE BASIS 
        OF NUMBER OF EXCITED LEVELS/13/ AND RESONANCE LEVEL       
        SPACING/14/.                                              
                                 AM-242     AM-241                
                      A(1/MEV)    29.6       29.0                 
                        T(MEV)    0.342      0.367                
                      C(1/MEV)    22.98      9.95                 
                      E-X(MEV)    2.323      3.122                
       SPIN-CUTOFF(1/MEV**0.5)    30.85      30.45                
                PAIRING E(MEV)    0.0        0.43                 
                                                                  
  MT=16,17   (N,2N) AND (N,3N) REACTION CROSS SECTIONS            
        JENDL-2 DATA CALCULATED WITH EVAPORATION MODEL WERE       
        ADOPTED.                                                  
                                                                  
  MT=18      FISSION CROSS SECTION                                
        EVALUATED ON THE BASIS OF THE DATA BY DABBS ET AL./8/     
                                                                  
  MT=102     CAPTURE CROSS SECTION                                
        EVALUATED ON THE BASIS OF THE MEASURED DATA OF VANPRAET ET
        AL./7/ IN THE UNRESOLVED RESONANCE REGION. ABOVE 30 KEV,  
        CALCULATION WITH CASTHY WAS ADOPTED.  THE GAMMA-RAY       
        STRENGTH FUNCTION WAS DETERMINED SO THAT THE CROSS SECTION
        WAS 1.7 BARNS AT 60 KEV.                                  
                                                                  
  MT=251     MU-BAR                                               
        CALCULATED WITH OPTICAL MODEL.                            
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-66,91       CALCULATED WITH CASTHY.                     
  MT=16,17,18         ISOTROPIC IN THE LAB SYSTEM.                
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,91         EVAPORATION SPECTRUM.                       
  MT=18               MAXWELLIAN FISSION SPECTRUM.  TEMPERATURE   
                      WAS ESTIMATED FROM Z**2/A VALUES /15/.      
                                                                  
REFERENCES                                                        
 1) KIKUCHI Y.: JAERI-M 82-096 (1982).                            
 2) NAKAGAWA T.: JAERI-M 88-008 (1989).                           
 3) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, P.29 (1979).            
 4) JAFFEY A.H. AND LERNER J.L.: NUCL.PHYS.,A145,1 (1970).        
 5) DERRIEN H. AND LUCAS B.: 1975 WASHINGTON, P.637,              
    NBS-SP-425 (1975).                                            
 6) KIKUCHI Y.: PRIVATE COMMUNICATION.                            
 7) VANPRAET G. ET AL.: 1985 SANTA FE, 1, 493 (1986).             
 8) DABBS J.W.T. ET AL.: NUCL. SCI. ENG., 83, 22 (1983).          
 9) IGARASI S.: J.NUCL.SCI.TECHNOL.,12,67 (1975).                 
10) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).              
11) PHILLIPS T.W. AND HOWE R.E.: NUCL. SCI. ENG., 69, 375 (1979). 
12) ELLIS-AKOVALI Y.A.: NUCL. DATA SHEETS, 44, 407 (1985).        
13) ENSDF, EVALUATED NUCLEAR STRUCTURE DATA FILE (1988).          
14) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL. 1, PART B",    
    ACADEMIC PRESS, INC. (1984).                                  
15) SMITH A.B. ET AL.: ANL/NDM-50 (1979).