96-Cm-245

 96-CM-245 JAERI      EVAL-MAR89 T.NAKAGAWA                       
                      DIST-MAR89 REV2-SEP92                       
----JENDL-3.2         MATERIAL 9640                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
78-03 EVALUATION WAS MADE BY S.IGARASI AND T.NAKAGAWA (JAERI)/1/. 
89-03 RE-EVALUATION FOR JENDL-3 WAS MADE BY T.NAKAGAWA(JAERI)/2/. 
90-07 SPIN IN MF2,MT151 WAS CORRECTED.                            
92-09 JENDL-3.2.                                                  
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (1,452), (1,456)                                            
     ***********************************************************  
                                                                  
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451  DESCRIPTIVE DATA                                        
  MT=452  NUMBER OF NEUTRONS PER FISSION                          
        SUM OF MT=455 AND MT=456.                                 
  MT=455  NUMBER OF DELAYED NEUTRONS PER FISSION                  
        ESTIMATED FROM THE SYSTEMATICS PROPOSED BY TUTTLE /3/.    
  MT=456  NUMBER OF PROMPT NEUTRONS PER FISSION                   
        EXPERIMENTAL RESULTS OF KHOKHLOV ET AL./4/ WERE ADOPTED.  
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151  RESONANCE PARAMETERS                                    
     RESOLVED RESONANCE REGION (SLBW) : 1.0E-5 TO 60 EV           
        PARAMETERS FOR REICH-MOORE FORMULA BY MOORE AND KEYWORTH  
        /5/ WERE ADOPTED ABOVE 20 EV, AND THOSE BY BROWNE ET AL.  
        /6/ BELOW 20 EV WITH A LITTLE MODIFICATION OF A NEGATIVE  
        RESONANCE SO THAT THE THERMAL CROSS SECTION COULD BE IN   
        AGREEMENT WITH THE EXPERIMENTAL DATA.  THE DIFFERENCES    
        BETWEEN REICH-MOORE AND SINGLE-LEVEL B-W FORMULAS ARE     
        TREATED AS THE BACKGROUND CROSS SECTIONS.                 
          RADIATIVE WIDTH   = 0.04 EV                             
          SCATTERING RADIUS = 10.0 FM                             
     UNRESOLVED RESONANCE PARAMETERS : 60 EV - 40 KEV             
        PARAMETERS WERE DETERMINED WITH A FITTING CODE ASREP/7/   
        SO AS TO REPRODUCE THE FISSION CROSS SECTION OF MOORE AND 
        KEYWORTH /5/, AND THE TOTAL AND CAPTURE CROSS SECTIONS    
        CALCULATED WITH OPTICAL AND STATISTICAL MODELS.           
          ENERGY INDEPENDENT PARAMETERS:                          
            R=9.43 FM, S0=1.02E-4, S1=2.24E-4, S2=0.9E-4,         
            WG=0.04 EV.                                           
          ENERGY DEPENDENT PARAMETERS AT 1 KEV:                   
            WF=2.01 EV, D=1.397 EV.                               
                                                                  
     CALCULATED 2200M/S CROSS SECTIONS AND RESONANCE INTEGRALS.   
                        2200 M/SEC      RES. INTEG.               
             TOTAL      2359.   B          -                      
             ELASTIC      11.59 B          -                      
             FISSION    2001.   B         801 B                   
             CAPTURE     346.4  B         110 B                   
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
     BELOW 40 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE 
     PARAMETERS.                                                  
                                                                  
  MT=1,2,4,51-73,91,102,251   TOTAL, ELASTIC AND INELASTIC        
     SCATTERING, CAPTURE CROSS SECTIONS AND MU-L                  
        CALCULATED WITH OPTICAL AND STATISTICAL MODEL CODE        
        CASTHY/8/.                                                
        THE SPHERICAL OPTICAL POTENTIAL PARAMETERS (MEV,FM):      
           V  =42.7-0.107*EN,              R  =1.282, A  =0.60    
           WS =6.95-0.339*EN+0.0531*EN**2, RS =1.29,  B  =0.50    
                (DERIVATIVE WOODS-SAXON FORM)                     
           VSO=7.0,                        RSO=1.282, ASO=0.60    
        THIS SET OF POTENTIAL PARAMETERS WAS DETERMINED /9/ TO    
        REPRODUCE WELL THE TOTAL CROSS SECTION OF AM-241 BY       
        PHILLIPS AND HOWE /10/.  THE STRENGTH FUNCTION OF 1.02E-4 
        CALCULATED WITH THIS OMP IS IN GOOD AGREEMENT WITH        
        1.18E-4/11/.                                              
                                                                  
        IN THE STATISTICAL MODEL CALCULATION, COMPETING PROCESSES 
        OF FISSION, (N,2N), (N,3N) AND (N,4N), AND LEVEL          
        FLUCTUATION WERE CONSIDERED.  THE LEVEL SCHEME OF CM-245  
        WAS TAKEN FROM THE COMPILATION BY ELLIS-AKOVALI /12/:     
              NO.     ENERGY(MEV)        SPIN-PARITY              
             G.S.       0.0                7/2 +                  
               1        0.0548             9/2 +                  
               2        0.1215            11/2 +                  
               3        0.1974            13/2 +                  
               4        0.25285            5/2 +                  
               5        0.2958             7/2 +                  
               6        0.35086            9/2 +                  
               7        0.35595            1/2 +                  
               8        0.3615             3/2 +                  
               9        0.3883             9/2 -                  
              10        0.4167            11/2 +                  
              11        0.4188             5/2 +                  
              12        0.431              5/2 +                  
              13        0.4429            11/2 -                  
              14        0.498             13/2 +                  
              15        0.5091            13/2 -                  
              16        0.532              9/2 +                  
              17        0.555             11/2 +                  
              18        0.63365            3/2 -                  
              19        0.6435             7/2 -                  
              20        0.66155            5/2 -                  
              21        0.7018             9/2 -                  
              22        0.722              7/2 +                  
              23        0.741              1/2 +                  
        OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.82 MEV.  LEVELS    
        WITH HIGHER SPIN THAN 13/2 OR WHOSE SPIN WAS UNKNOWN WERE 
        NEGLECTED.  THE LEVEL DENSITY PARAMETERS WERE DETERMINED  
        ON THE BASIS OF NUMBERS OF EXCITED LEVELS/13/ AND         
        RESONANCE LEVEL SPACING/11/.                              
                                 CM-246    CM-245                 
                      A(1/MEV)    27.7      30.0                  
                        T(MEV)    0.395     0.391                 
                      C(1/MEV)    2.2560    11.288                
                      E-X(MEV)    4.1307    4.0295                
       SPIN-CUTOFF(1/MEV**0.5)    30.17     31.31                 
                PAIRING E(MEV)    1.11      0.72                  
                                                                  
        AVERAGE RADIATIVE WIDTH = 0.040 EV AND D = 1.4 EV /11/    
        WERE USED FOR THE CAPTURE CROSS SECTION CALCULATION.      
                                                                  
  MT=16,17,37  (N,2N). (N,3N) AND (N,4N) CROSS SECTIONS           
        CALCULATED WITH THE EVAPORATION MODEL BY PEARLSTEIN /14/. 
        NEUTRON EMISSION CROSS SECTION WAS ASSUMED TO BE (COMPOUND
        NUCLEUS FORMATION CROSS SECTION CALCULATED WITH OPTICAL   
        MODEL - FISSION).                                         
                                                                  
  MT=18 FISSION CROSS SECTION                                     
        BELOW 100 KEV: JENDL-2 WAS ADOPTED, WHICH WAS OBTAINED BY 
                       FITTING A SEMI-EMPIRICAL FORMULA TO THE    
                       EXPERIMENTAL DATA OF REF./5/.              
        ABOVE 100 KEV: BASED ON THE EXPERIMENTAL DATA OF WHITE    
                       AND BROWNE /15/.                           
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-73,91                                                   
        LEGENDRE COEFFICIENTS WERE GIVEN BY THE OPTICAL AND       
        STATISTICAL MODEL CALCULATIONS.                           
  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                             
  MT=18    FISSION SPECTRUM ESTIMATED FROM Z**2/A SYSTEMATICS BY  
           SMITH ET AL./16/ BY ASSUMING E(CF-252) = 2.13 MEV.     
                                                                  
REFERENCES                                                        
 1) IGARASI S. AND NAKAGAWA T.: JAERI-M 7733 (1978).              
 2) NAKAGAWA T.: JAERI-M 90-101 (1990).                           
 3) TUTTLE R.J.: PROC. CONSULTANTS' MEETING ON DELAYED NEUTRON    
    PROPERTIES, 1973 VIENNA, 29, ALSO INDC(NDS)-107/G+SPECIAL     
    (1979).                                                       
 4) KHOKHLOV YU.A. ET AL.: INT. SEMINAR ON INTERACTION OF NEUTRONS
    WITH NUCLEI, 1992 DUBUNA, NO.5.5 (1992).                      
 5) MOORE M.S. AND KEYWORTH G.A.: PHYS. REV., C3, 1656 (1971).    
 6) BROWNE J.C. ET AL. : NUCL. SCI. ENG., 65, 166 (1978).         
 7) KIKUCHI Y.: PRIVATE COMMUNICATION.                            
 8) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
 9) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).              
10) PHILLIPS T.W. AND HOWE R.E.: NUCL. SCI. ENG. 69, 375 (1979).  
11) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL.1, PART B",     
    ACADEMIC PRESS (1984).                                        
12) ELLIS-AKOVALI Y.A.: NUCL. DATA SHEETS, 33, 119 (1981).        
13) ENSDF, EVALUATED NUCLEAR STRUCTURE DATA FILE, AS OF JAN. 1989.
14) PEARLSTEIN S.: NUCL. SCI. ENG., 23, 238 (1965).               
15) WHITE R.M. AND BROWNE J.C.: 1983 ANTWERP, 218 (1983).         
16) SMITH A.B. ET AL.: ANL/NDM-50 (1979).