90-Th-233

 90-TH-233 KINKI U.   EVAL-JUL87 T.OHSAWA                         
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 9043                               
-----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 ADDED.  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 THERMAL CAPTURE CROSS SECTION OF    
      1450+-100 BARNS WAS ADOPTED FROM REF./7/, AND THE THERMAL   
      FISSION CROSS SECTION OF 15 BARNS FROM LLL EVALUATED NUCLEAR
      DATA LIBRARY/8/.  THE CAPTURE AND FISSION CROSS SECTIONS AT 
      0.0253 EV WERE EXTRAPOLATED UP TO 200 EV BY ASSUMING THE    
      FORM OF 1/V FOR THE FORMER, AND UP TO 20 KEV BY ASSUMING THE
      FORM OF 1/V PLUS THE CONSTANT VALUE OF 0.3 BARNS FOR THE    
      LATTER.                                                     
                                                                  
      CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEG.(BARNS)   
                        2200-M/S      RES. INTEG.                 
              TOTAL      1478.0          -                        
              ELASTIC      13.0          -                        
              FISSION      15.0          11.1                     
              CAPTURE    1450.0         643                       
                                                                  
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=4,51-65,91  INELASTIC SCATTERING CROSS SECTION               
      STATISTICAL AND OPTICAL MODEL CALCULATIONS.                 
                                                                  
          LEVEL SCHEME OF TH-233 /11/.                            
             NO.      ENERGY(MEV)  SPIN-PARITY                    
              G.S.    0.0           1/2 +                         
              1       0.01687       3/2 +                         
              2       0.05456       5/2 +                         
              3       0.09363       7/2 +                         
              4       0.37121       5/2 +                         
              5       0.53958       1/2 -                         
              6       0.58393       1/2 +                         
              7       0.6115        3/2 +                         
              8       0.62902       5/2 +                         
              9       0.6822        3/2 -                         
             10       0.7135        1/2 +                         
             11       0.7218        3/2 +                         
             12       0.7695        5/2 +                         
             13       0.8145        3/2 +                         
             14       0.8914        3/2 +                         
             15       0.9476        3/2 -                         
          LEVELS ABOVE 0.95 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 /12/.                                                 
  MT=18   FISSION CROSS SECTION                                   
      FISSION PROBABILITY DEDUCED FROM DIRECT REACTION /13, 14/   
      WAS USED TO CALCULATE THE FISSION CROSS SECTION.            
  MT=102  CAPTURE CROSS SECTION                                   
      STATISTICAL AND OPTICAL MODEL CALCULATIONS WITH GAMMA-RAY   
      STRENGTH FUNCTION OF 0.00352.                               
  MT=251  MU-BAR                                                  
      CALCULATED WITH OPTICAL MODEL.                              
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-65,91                                                   
      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.                                        
  MT=18                                                           
      FISSION SPECTRUM ESTIMATED FROM Z**2/A SYSTEMATICS OF SMITH 
      ET AL. /15/                                                 
                                                                  
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) JOHNSTONE F.J. AND HALPERIN J.: J. NUCL. ENERGY, 11, 95(1960).
 8) UCRL-50400, VOL. 15, PART D (1977).                           
 9) OHSAWA T. AND OHTA M.: J. NUCL. SCI. TECHNOL. 18, 408 (1981). 
10) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
11) LEDERER C.M. AND SHIRLY V.S. (ED.): TABLE OF ISOTOPES,        
    7TH EDITION (1978).                                           
12) SEGEV M. AND CANER M.: ANN. NUCL. ENERGY 5, 239(1978).        
13) BACK B.B. ET AL.: PHYS. REV. C13, 2374 (1974).                
14) CRAMER J.D. AND BRITT H.C.: NUCL. SCI. ENG. 41, 177 (1970).   
15) SMITH A.B. ET AL.: ANL/NDM-50 (1979).