93-Np-239

 93-NP-239 KYUSHU U.+ EVAL-MAR76 Y.KANDA, JENDL-CG                
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 9352                               
-----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                                                           
76-03 THE EVALUATION FOR JENDL-1 WAS PERFORMED BY KANDA (KYUSHU   
      UNIV.) AND JENDL-1 COMPILATION GROUP.  DETAILS ARE GIVEN    
      IN REF. /1/.                                                
83-03 JENDL-1 DATA WERE ADOPTED FOR JENDL-2 AND EXTENDED TO 20    
      MEV.  MF=5 WAS REVISED.                                     
87-07 DATA FORMAT WAS CONVERTED INTO ENDF-5 FORMAT AND ADOPTED    
      TO JENDL-3.                                                 
94-06 JENDL-3.2.                                                  
       NU-P, NU-D AND NU-TOTAL WERE MODIFIED.                     
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (1,452), (1,455), (1,456)                                   
     ***********************************************************  
                                                                  
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451  DESCRIPTIVE DATA AND DICTIONARY                         
  MT=452 NUMBER OF NEUTRONS PER FISSION                           
     SUM OF NU-P NAD NU-D.                                        
  MT=455 DELAYED NEUTRONS PER FISSION                             
     AVERAGE VALUES OF SYSTEMATICS BY TUTTLE/2/, BENEDETTI ET     
     AL./3/ AND WALDO ET AL./4/  DECAY CONSTANTS WERE ASSUMED TO  
     BE THE SAME AS THOSE OF NP-237 EVALUATED BY BRADY AND        
     ENGLAND/5/.                                                  
  MT=456 PROMPT NEUTRONS PER FISSION                              
     BASED ON SYSTEMATICS BY MANERO AND KONSHIN/6/, AND BY        
     HOWERTON/7/.                                                 
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151 NO RESONANCE PARAMETERS WERE GIVEN.                      
                                                                  
     2200-M/SEC CROSS SECTIONS AND CALCULATED RESONANCE INTEGRALS.
                       2200 M/SEC        RES. INTEG.              
         TOTAL          47.50 B             -                     
         ELASTIC        10.50 B             -                     
         FISSION         0.0  B            7.06 B                 
         CAPTURE        37.00 B          445.   B                 
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  BELOW 4.0 EV.                                                   
  MT=1    TOTAL                                                   
     SUM OF PARTIAL CROSS SECTIONS.                               
  MT=2    ELASTIC SCATTERING                                      
     THE CONSTANT CROSS SECTION OF 10.5 BARNS WAS ASSUMED FROM    
         SIG=4*3.14*(0.147*A**(1/3))**2.                          
  MT=18   FISSION                                                 
     ASSUMED TO BE ZERO BARNS.                                    
  MT=102  CAPTURE                                                 
     THE FORM OF 1/V WAS ASSUMED.  THE 2200-M/SEC CROSS SECTION   
     WAS ADOPTED FROM THE EXPERIMENTAL DATA BY STOUGHTON AND      
     HALPERIN /8/.                                                
  ABOVE 4.0 EV.                                                   
  MT=1    TOTAL                                                   
     CALCULATED WITH OPTICAL AND STATISTICAL MODEL CODE CASTHY    
     /9/.  OPTICAL POTENTIAL PARAMETERS WERE OBTAINED BY OHTA AND 
     MIYAMOTO /10/ BY USING THE TOTAL CROSS SECTION OF PU-239.    
        V = 45.87-0.2*EN, WI= 0.06, WS= 14.1, VSO= 7.3 (MEV)      
        R = 1.27        , RI= 1.27, RS=1.302, RSO= 1.27(FM)       
        A0= 0.652       , AI=0.315, AS= 0.98, ASO=0.652(FM)       
  MT=2  ELASTIC SCATTERING                                        
     CALCULATED WITH CASTHY /9/.                                  
  MT=4,51-58,91  INELASTIC SCATTERING                             
     CALCULATED WITH CASTHY /9/.  THE LEVEL SCHEME WAS ADOPTED    
     FROM NUCL. DATA SHEETS VOL.6.                                
           NO.     ENERGY(MEV)  SPIN-PARITY                       
          G.S.      0.0          5/2 +                            
            1       0.03114      7/2 +                            
            2       0.07112      9/2 +                            
            3       0.07467      5/2 -                            
            4       0.11766     11/2 +                            
            5       0.1230       7/2 -                            
            6       0.17305      9/2 -                            
            7       0.2414      11/2 -                            
            8       0.320       13/2 -                            
     LEVELS ABOVE 430 KEV WERE ASSUMED TO OVERLAPPING.  IN THE    
     CALCULATION THE CAPTURE, FISSION, (N,2N) AND (N,3N) CROSS    
     SECTIONS WERE CONSIDERED AS COMPETING PROCESSES.             
  MT=16,17  (N,2N) AND (N,3N)                                     
     CALCULATED WITH PEARLSTEIN'S METHOD /11/.                    
  MT=18  FISSION                                                  
     ESTIMATED FROM THE NP-237 FISSION CROSS SECTION BY NORMALI-  
     ZING WITH NEUTRON SEPARATION ENERGIES.                       
  MT=102  CAPTURE                                                 
     BELOW 100 KEV, THE CROSS SECTION WAS CALCULATED FROM         
         SIG = 435 / SQRT(EN) BARNS.                              
     ABOVE 100 KEV, THE SHAPE OF THE EXPERIMENTAL DATA FOR NP-237 
     BY NAGLE ET AL. /12/ WAS ADOPTED AND NORMALIZED TO 1.4 BARNS 
     AT 100 KEV.                                                  
  MT=251 MU-BAR                                                   
     CALCULATED WITH CASTHY /9/.                                  
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2               CALCULATED WITH CASTHY CODE /9/.             
  MT=51-58           ISOTROPIC IN THE CENTER-OF-MASS SYSTEM.      
  MT=16,17,18,91     ISOTROPIC IN THE LABORATORY SYSTEM.          
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,91        EVAPORATION SPECTRUM.                        
  MT=18              MAXWELLIAN FISSION SPECTRUM ESTIMATED FROM   
                     Z**2/A SYSTEMATICS /13/.                     
                                                                  
REFERENCES                                                        
 1) IGARASI S. ET AL.: JAERI 1261 (1979).                         
 2) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, P.29 (1979),            
 3) BENEDETTI G. ET AL.: NUCL. SCI. ENG., 80, 379 (1982).         
 4) WALDO R. ET AL.: PHYS. REV., C23, 1113 (1981).                
 5) BRADY M.C. AND ENGLAND T.R.: NUCL. SCI. ENG., 103, 129 (1989).
 6) MANERO F. AND KONSHIN V.A.:  AT. ENERGY REV.,10, 637 (1972).  
 7) HOWERTON R.J.: NUCL. SCI. ENG.,62, 438 (1977).                
 8) STOUGHTON R.W. AND HALPERIN J.: NUCL. SCI. ENG., 6, 100       
    (1959).                                                       
 9) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
10) OHTA M. AND MIYAMOTO K.: J. NUCL. SCI. TECHNOL., 10, 583      
    (1973).                                                       
11) PEARLSTEIN S.: NUCL. SCI. ENG., 23, 238 (1965).               
12) NAGEL R.J. ET AL.: 1971 KNOXVILLE CONF., 259 (1971).          
13) SMITH A.B. ET AL.: ANL/NDM-50 (1979).