90-Th-234

 90-TH-234 KINKI U.   EVAL-JUL87 T.OHSAWA                         
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 9046                               
-----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                                                           
81-04 EVALUATION FOR JENDL-2 WAS MADE BY T. OHSAWA AND M. OHTA    
      (KYUSHU UNIVERSITY: PRESENT ADDRESS OF OHSAWA IS KINKI      
      UNIV.).  DETAILS OF THE EVALUATION ARE DESCRIBED IN REF.    
      /1/.                                                        
83-11 FISSION SPECTRUM WAS GIVEN.  THE TOTAL, (N,2N) AND (N,3N)   
      CROSS SECTIONS WERE MODIFIED.                               
87-07 JENDL-2 DATA WERE ADOPTED FOR JENDL-3.                      
         COMPILATION WAS MADE BY T.NAKAGAWA(JAERI).               
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 COMMENT 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 TH-232 EVALUATED BY BRADY AND    
      ENGLAND/5/.                                                 
  MT=456 PROMPT NEUTRONS PER FISSION                              
      BASED ON THE SEMI-EMPIRICAL FORMULA OF HOWERTON /6/.        
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151  RESOLVED RESONANCES                                     
      NO RESOLVED RESONANCES WERE ADOPTED, SINCE THERE WERE NO    
      MEASUREMENTS MADE.  THE CAPTURE CROSS SECTION AT 0.0253 EV  
      /7/ WAS EXTRAPOLATED ON AN 1/V BASIS UP TO AN ENERGY OF 15  
      EV. THE FISSION CROSS SECTION AT 0.0253 EV IS LESS THAN 0.02
      BARN /8/, THEREFORE IT WAS ASSUMED TO 0.0 BARN.             
                                                                  
      CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEG.(BARNS)   
                        2200-M/S       RES. INTEG.                
              TOTAL        14.75           -                      
              ELASTIC      13.0            -                      
              FISSION       0.0             0.26                  
              CAPTURE       1.75           93.7                   
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  MT=1    TOTAL CROSS SECTION                                     
      OPTICAL MODEL CALCULATION WITH THE FOLLOWING PARAMETERS:    
         V  = 41.0 - 0.05*E      (MEV),                           
         WS = 6.4 + 0.15*SQRT(E) (MEV),  -- DER. WOODS-SAXON --   
         VSO= 7.0                (MEV),                           
         R0 = RSO = 1.31         (FM),                            
         RS = 1.38               (FM),                            
         A  = B  = ASO= 0.47     (FM).                            
      THESE PARAMETERS WERE TAKEN FROM THOSE FOR TH-232 /9/.      
  MT=2    ELASTIC SCATTERING CROSS SECTION                        
      STATISTICAL AND OPTICAL MODEL CALCULATIONS USING THE CODE   
      CASTHY /10/.                                                
  MT=4,51-67,91  INELASTIC SCATTERING CROSS SECTION               
      STATISTICAL AND OPTICAL MODEL CALCULATIONS.                 
                                                                  
          LEVEL SCHEME OF TH-234 (ESTIMATED FROM SYSTEMATICS)     
             NO.      ENERGY(MEV)  SPIN-PARITY                    
              G.S.    0.0             0 +                         
              1       0.048           2 +                         
              2       0.160           4 +                         
              3       0.336           6 +                         
              4       0.576           8 +                         
              5       0.730           0 +                         
              6       0.767           2 +                         
              7       0.785           2 +                         
              8       0.853           4 +                         
              9       0.882           1 -                         
             10       0.889           4 +                         
             11       0.942           3 -                         
             12       0.987           6 +                         
             13       1.050           5 -                         
             14       1.053           6 +                         
             15       1.073           8 +                         
             16       1.206           7 +                         
             17       1.277           8 +                         
          LEVELS ABOVE 1.06 MEV WERE ASSUMED TO BE OVERLAPPING.   
                                                                  
  MT=16,17  (N,2N) AND (N,3N) CROSS SECTIONS                      
      CALCULATED BY MEANS OF THE EVAPORATION MODEL OF SEGEV AND   
      CANER /11/.                                                 
  MT=18   FISSION CROSS SECTION                                   
      FISSION PROBABILITY DEDUCED FROM DIRECT REACTION /12/ AND   
      SYSTEMATICS OF BEHRENS /13/ WERE USED TO OBTAIN FISSION     
      CROSS SECTION.                                              
  MT=102  CAPTURE CROSS SECTION                                   
      STATISTICAL AND OPTICAL MODEL CALCULATIONS WITH GAMMA-RAY   
      STRENGTH FUNCTION OF 0.00791.                               
  MT=251  MU-BAR                                                  
      CALCULATED WITH OPTICAL MODEL.                              
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-67,91                                                   
      STATISTICAL AND OPTICAL MODEL CALCULATIONS.                 
  MT=16,17,18                                                     
      ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.           
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,91                                                     
      EVAPORATION SPECTRA WERE GIVEN.                             
  MT=18                                                           
      FISSION SPECTRUM WAS ESTIMATED FROM Z**2/A SYSTEMATICS      
      OF SMITH ET AL. /14/.                                       
                                                                  
REFERENCES                                                        
 1) OHSAWA T. AND OHTA M.: MEMOIRS FACULTY OF ENGINEERING,        
    KYUSHU UNIV. 40, 149 (1980).                                  
 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) HOWERTON R.J.: NUCL. SCI. ENG. 62, 438 (1977).                
 7) HARVEY B.G. AND PARSONS B.I.: PHYS. REV., 80, 1098 (1950).    
 8) OSBORNE C. AND COVEYOU I.: MON-P-178, P.10 (1948), AS CITED IN
    HUIZENGA J.R. ET AL. "THE ACTINIDE ELEMENTS", NATIONAL NUCLEAR
    ENERGY SERIESEM DIV. IV, VOL.14A (ED. SEABORG ET AL.)  P.839  
    (1954).                                                       
 9) OHSAWA T. AND OHTA M.: J. NUCL. SCI. TECHNOL. 18, 408 (1981). 
10) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
11) SEGEV M. AND CANER M.: ANN. NUCL. ENERGY 5, 239(1978).        
12) BACK B.B. ET AL.: PHYS. REV. C13, 2374 (1974).                
13) BEHRENS J.W.: UCID-17509-2 (1977); PHYS. REV. LETT. 39, 68    
    (1977).                                                       
14) SMITH A.B. ET AL.: ANL/NDM-50 (1979).