93-Np-237

 93-NP-237 KYUSHU U.+ EVAL-NOV87 Y.UENOHARA, Y.KANDA              
                      DIST-JAN88 REV2-AUG93                       
----JENDL-3.2         MATERIAL 9346                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
79-03 NEW EVALUATION WAS MADE BY N.WACHI AND Y.KANDA (KYUSHU      
      UNIVERSITY), AND Y.KIKUCHI (JAERI).                         
87-11 (N,2N), (N,3N) AND FISSION CROSS SECTIONS WERE RE-EVALUATED 
      IN THE ENERGY RANGE ABOVE 100 KEV BY Y.UENOHARA AND Y.KANDA 
      (KYUSHU UNIVERSITY).                                        
88-01 COMPILED BY T.NAKAGAWA (JAERI).                             
        MODIFIED QUANTITIES : (1,452), (1,456), (3,2), (3,16)     
                              (3,17) AND (3,18)                   
89-02 FP YIELDS WERE TAKEN FROM JNDC FP DECAY FILE VERSION-2.     
89-03 (N,2N) REACTION CROSS SECTION WAS MODIFIED.                 
93-08 JENDL-3.2.                                                  
      MODIFIED BY T.NAKAGAWA (NDC/JAERI)                          
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (2,151)                                                     
      (3,18)             BELOW 350 KEV                            
      (8,16)                                                      
      (9,16)                                                      
     ***********************************************************  
                                                                  
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451   COMMENTS AND DICTIONARY                                
  MT=452   NUMBER OF NEUTRONS PER FISSION                         
              SUM OF MT=455 AND MT=456.                           
  MT=455   DELAYED NEUTRON DATA                                   
              EXPERIMENTAL DATA OF BENEDETTI+/1/ AND SYSTEMATICS  
              BY TUTTLE/2/.                                       
  MT=456   NUMBER OF NEUTRONS PER FISSION                         
              BASED ON EXPERIMENTAL DATA OF FREHAUT+/3/.          
                                                                  
MF=2, MT=151  RESONANCE PARAMETERS                                
   RESOLVED RESONANCES FOR SLBW FORMULA : 1.0E-5 - 130 EV         
           RES. ENERGY, GAM-N, GAM-G:  WESTON AND TODD /4/.       
           GAM-F                    :  PLATTARD+ /5/.             
             --> FOR JENDL-3.2, 5 TIMES LARGE VALUES ARE USED ON  
                 THE BASIS OF NEW MEASUREMENT AT KYOTO UNIV./6/.  
           AVERAGE GAM-G = 40 MILLI-EV.                           
           TWO NEGATIVE RESONANCE ARE GIVEN.  PARAMETERS OF       
           0.22-EV RESONACE WERE ADJUSTED SO AS TO REDUCE THE     
           THERMAL CAPTURE CROSS SECTION/7/                       
   UNRESOLVED RESONANCES  : 130 EV - 30 KEV                       
        PARAMETERS BY WESTON AND TODD/4/ WITH SLIGHT MODIFICATION 
        ADOPTED PARAMETERS :                                      
           S0=1.02E-4 , S1=1.888E-4 , D-OBS=0.45 EV               
           GAM-G=40 MILLI-EV.                                     
        GAM-F VALUES DETERMINED SO THAT SIG-F = 0.009 B.          
                                                                  
   CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS:    
                       2200 M/S VALUE      RES.INT.               
           TOTAL   :     192.11  B           -                    
           ELASTIC :      27.44  B           -                    
           FISSION :     0.0225  B          7.06  B               
           CAPTURE :     164.6   B         662    B               
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  MT=1,4,51-64,91,102,251   TOTAL, INELASTIC, CAPTURE AND MU-BAR  
        CALCULATED WITH OPTICAL AND STATISTICAL MODEL CODE CASTHY 
        /8/.                                                      
            THE SPHERICAL OPTICAL POTENTIAL PARAMETERS :          
               V = 43.55      ,  WS = 11.0  ,  VSO = 7.0   (MEV)  
               R = RS = 1.32  ,  RSO= 1.3                  (FM)   
               A = B  = 0.47  ,  ASO= 0.4                  (FM).  
        IN THE STATISTICAL MODEL CALCULATION WITH CASTHY CODE,    
        COMPETING PROCESSES, FISSION, (N,2N) AND (N,3N), AND LEVEL
        FLUCTUATION WERE CONSIDERED.  THE LEVEL SCHEME WAS TAKEN  
        FROM COMPILATION BY ELLIS /9/.                            
                    NO        ENERGY(MEV)        SPIN-PARITY      
                   G.S.          0.0                5/2+          
                     1           0.03320            7/2+          
                     2           0.05954            5/2-          
                     3           0.07580            9/2+          
                     4           0.10296            7/2-          
                     5           0.13000           11/2+          
                     6           0.15852            9/2-          
                     7           0.2260            11/2-          
                     8           0.26754            3/2-          
                     9           0.281              1/2-          
                    10           0.305             13/2-          
                    11           0.327              7/2-          
                    12           0.332              1/2+          
                    13           0.357              5/2-          
                    14           0.369              5/2+          
             CONTINUUM LEVELS ASSUMED ABOVE 0.370 MEV.            
        THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM GILBERT AND  
        CAMERON /10/.  THE GAMMA-RAY STRENGTH FUNCTION FOR THE    
        CAPTURE CROSS SECTION WAS DETERMINED SO THAT SIG-C = 0.742
        B AT 200 KEV.                                             
                                                                  
  MT=2             ELASTIC SCATTERING                             
        CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS).    
                                                                  
  MT=16            (N,2N)                                         
        FOR JENDL-2, DATA WERE CALCULATED WITH THE EVAPORATION    
        MODEL OF SEGEV+/11/.  THE DATA FOR JENDL-3 WERE EVALUATED 
        BY FITTING TO THE FOLLOWING EXPERIMENTAL DATA.            
           PERKIN+ /12/, LANDRUM+ /13/, LINDKE+ /14/, FORT+ /15/, 
           GROMOVA+ /16/ AND KORNILOV+ /17/.                      
        THE DATA OF JENDL-2 WERE USED AS PRIOR VALUES, AND 50%    
        FRACTIONAL STANDARD DEVIATIONS WERE ASSIGNED TO THEM.     
                                                                  
  MT=17            (N,3N)                                         
        FOR JENDL-2, CALCULATED WITH THE EVAPORATION MODEL OF     
        SEGEV+ /11/.  ABOVE 16.5 MEV, THE JENDL-2 DATA WERE       
        MODIFIED BY ADDING THE VALUES OF (SIG-2N OF JENDL-2)-     
        (SIG-2N OF JENDL-3).  BELOW 16.5 MEV, THE SHAPE OF (N,3N) 
        CROSS SECTION OF JENDL-2 WAS NORMALIZED TO THE MODIFIED   
        VALUE AT 16.5 MEV.                                        
                                                                  
  MT=18            FISSION                                        
        EVALUATED FROM MEASURED DATA.  ABOVE 100 KEV, SIMULTANEOUS
        EVALUATION METHOD WAS USED BY TAKING ACCOUNT OF THE       
        FOLLOWING EXPERIMENTAL DATA.                              
          KLEMA /18/, PROTOPOPOV+ /19/, SCHMITT+ /20/, GRUNDL     
          /21/, IYER+ /22/, JIACOLETTI+ /23/, KOBAYASHI+ /24/,    
          ARLT+ /25/, CANCE+ /26/, GARLEA+ /27/, KUPRIJANOV+ /28/,
          WHITE+ /29,30/, STEIN+ /31/, BEHRENS+ /32/ AND MEADOWS  
          /33/.                                                   
        FOR JENDL-3.2, CROSS SECTIONS BELOW 350 KEV WAS MODIFIOED 
        AS AS TO SMOOTHLY CONNECT TO THE DATA MESURED BY YAMANAKA+
        /6/                                                       
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-64,91   CALCULATED WITH THE OPTICAL MODEL.              
  MT=16,17,18     ISOTROPIC IN THE LABORATORY SYSTEM.             
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,91     EVAPORATION SPECTRUM.                           
  MT=18           ESTIMATED FROM Z**2/A SYSTEMATICS BY SMITH+/34/ 
                  BY ASSUMING E(CF-252) = 2.13 MEV.               
                                                                  
MF=8  RADIOACTIVE DECAY                                           
  MT=16                                                           
      DECAY DATA OF NP-236 ARE GIVEN.                             
                                                                  
MF=9  MULTIPLICITIES FOR PRODUCTION OF RADIOACTIVE NUCLIDES       
  MT=16                                                           
      META-STABLE STATE (T-1/2 =22.5 H) PRODUCTIOIN WAS ASSUMED TO
      BE 75 %.                                                    
                                                                  
REFERENCES                                                        
 1) G. BENEDETTI ET AL.:  NUCL. SCI. ENG., 80, 379 (1982).        
 2) R.J. TUTTLE: INDC(NDS)-107/G+SPECIAL, P.29 (1979).            
 3) J. FREHAUT ET AL.:  CEA-N-2196 (1981).                        
 4) L.W. WESTON AND J.H. TODD: NUCL. SCI. ENG., 79, 184 (1981).   
 5) S. PLATTARD ET AL.: NUCL. SCI. ENG., 61, 477 (1976).          
 6) A. YAMANAKA, ET AL: J. NUCL. SCI. TECHNOL., 30, 863 (1993).   
 7) K. KOBAYASHI, ET AL: TO BE PUBLISHED IN JAERI-M REPORT(1994). 
 8) S. IGARASI AND T. FUKAHORI: JAERI 1321 (1991).                
 9) Y.A. ELLIS: NUCL. DATA SHEETS, B6, 539 (1971).                
10) A. GILBERT AND A.G.W. CAMERON:  CAN. J. PHYS., 43, 1446 (1965)
11) M. SEGEV ET AL.: ANNALS OF NUCL. ENERGY, 5, 239 (1978).       
12) J. PERKIN, ET AL.: NUCL. ENERG., 14, 69 (1961).               
13) J. LANDRUM, ET AL.: PHYS. REV., C8, 1938 (1969).              
14) K.E.A.LINDKE: PHYS. REV., C12, 1507 (1975).                   
15) E. FORT, ET AL.: 82ANTWERP, 673 (1982).                       
16) E.A. GROMOVA, ET AL.: AT. ENERG., 54, 108 (1983).             
17) N.V. KORNILOV, ET AL.: AT. ENERG., 58, 117 (1983).            
18) E.D. KLEMA: PHYS. REV., 72, 88, (1947).                       
19) A.N. PROTOPOPOV, ET AL.: AT. ENERG., 4, 190 (1958).           
20) H.W. SCHMITT, ET AL.: PHYS. REV., 116, 1575 (1959).           
21) J.A. GRUNDL: NUCL. SCI. ENG., 30, 39 (1967).                  
22) R.H. IYER, ET AL.: 69ROORKEE, 2, 289 (1969).                  
23) R.J. JIACOLETTI, ET AL.: NUCL. SCI. ENG., 48, 412 (1972).     
24) K. KOBAYASHI, ET AL.: PRIVATE COMMUNICATION (1973).           
25) R. ARLT, ET AL.: KERNENERGIE 24, 48 (1981).                   
26) M. CANCE, ET AL.: 82ANTWERP, 51 (1982).                       
27) I. GARLEA, ET AL.: INDC(ROM)-15 (1983).                       
28) V.M. KUPRIJANOV, ET AL.: AT. ENERG, 45, 440 (1978).           
29) P.H. WHITE, ET AL.: 65SALZBURG, 1, 219 (1965).                
30) P.H. WHITE, ET AL.: J. NUCL. ENERG., 21, 671 (1967).          
31) W.E. STEIN, ET AL.: 68WASHIGTON, 1, 627 (1968).               
32) J.W. BEHRENS, ET AL.: NUCL. SCI. ENG., 80, 393 (1982).        
33) J.W. MEADOWS: NUCL. SCI. ENG., 85, 271 (1983).                
34) A.B. SMITH ET AL.: ANL/NDM-50 (1979).