90-Th-230

 90-TH-230 KINKI U.   EVAL-JUL87 T.OHSAWA                         
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 9034                               
-----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     
      UNIVERSITY).  DETAILS OF EVALUATION ARE DESCRIBED IN REF.   
      /1/.                                                        
83-11 FISSION SPECTRUM WAS ADDED.  RESONANCE PARAMETERS, AND      
      TOTAL, (N,2N) AND (N,3N) CROSS SECTIONS WERE MODIFIED.      
87-07 EVALUATION FOR JENDL-2 WAS ADOPTED TO JENDL-3.  BUT RE-     
      CALCULATION OF CROSS SECTIONS AND ANGULAR DISTRIBUTIONS     
      WAS MADE WITH THE SAME OMP AND LEVEL DENSITY PARAMETERS.    
          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-229 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                                     
      RESONANCE REGION IS BELOW 564.26 EV.  THE MLBW FORMULA WAS  
      SELECTED TO REPRODUCE RESONANCE CROSS SECTIONS.  A TOTAL    
      NUMBER OF 28 RESONANCES UP TO 563 EV MEASURED BY KALEBIN ET 
      AL. /7/ WERE ADOPTED IN THE PRESENT EVALUATION.             
      A BACKGROUND TERM WITH 1/V DEPENDENCE WAS ADDED IN ORDER TO 
      REPRODUCE THE THERMAL CAPTURE CROSS SECTION.                
                                                                  
      CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEG.(BARNS)   
                         2200-M/S       RES. INTEG.               
              TOTAL        32.32           -                      
              ELASTIC       9.774          -                      
              FISSION       0.0             1.08                  
              CAPTURE      22.55         1040                     
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
       BELOW 564.26 EV IS THE RESONANCE REGION WHERE THE          
       BACKGROUND CROSS SECTIONS ARE GIVEN.  ABOVE 564.26 EV, THE 
       CROSS SECTIONS WERE EVALUATED AS FOLLOWS.                  
                                                                  
  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 /8/.      
  MT=2    ELASTIC SCATTERING CROSS SECTION                        
      STATISTICAL AND OPTICAL MODEL CALCULATIONS USING THE CODE   
      CASTHY /9/.                                                 
  MT=4,51-63,91  INELASTIC SCATTERING CROSS SECTION               
      STATISTICAL AND OPTICAL MODEL CALCULATIONS.                 
                                                                  
          LEVEL SCHEME OF TH-230 /10/.                            
             NO.      ENERGY(MEV)  SPIN-PARITY                    
              G.S.    0.0           0 +                           
              1       0.0534        2 +                           
              2       0.173         4 +                           
              3       0.357         6 +                           
              4       0.506         1 -                           
              5       0.571         3 -                           
              6       0.635         0 +                           
              7       0.678         2 +                           
              8       0.682         5 -                           
              9       0.781         2 +                           
             10       0.881         4 +                           
             11       0.951         1 -                           
             12       1.009         2 +                           
             13       1.012         3 -                           
          LEVELS ABOVE 1.02 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                                   
      EVALUATION WAS MADE ON THE BASIS OF THE DATA OF MUIR ET     
      AL. /12/ UP TO 2 MEV.  ABOVE 2 MEV, THE FISSION PROBABILITY 
      DATA OF BACK ET AL. /13/ WERE USED TO CALCULATE THE 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 CASTHY.                                     
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-63,91                                                   
      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 BY 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) KALEBIN S.M. ET AL.: SOV. J. ATOM. ENERGY 26, 588 (1969).     
 8) OHSAWA T. AND OHTA M.: J. NUCL. SCI. TECHNOL. 18, 408 (1981). 
 9) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
10) LEDERER C.M. AND SHIRLY V.S. (ED.): TABLE OF ISOTOPES,        
    7TH EDITION (1978).                                           
11) SEGEV M. AND CANER M.: ANN. NUCL. ENERGY 5, 239(1978).        
12) MUIR D.W. ET AL.: PROC. 3RD CONF. ON NEUTRON CROSS SECTIONS   
    AND TECHNOLOGY, KNOXVILLE (1971), P.292.                      
13) BACK B.B. ET AL.: PHYS. REV. C13, 2374 (1974).                
14) SMITH A.B. ET AL.: ANL/NDM-50 (1979).