90-Th-229

 90-TH-229 TIT        EVAL-AUG88 N.TAKAGI                         
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 9031                               
-----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                                                           
87-08 NEW EVALUATION WAS MADE BY N. TAKAGI (TOKYO INSTITUTE OF    
      TECHNOLOGY, TIT) /1/.                                       
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 ADOPTED   
       FROM THE EVALUATION 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   RESOLVED RESONANCE PARAMETERS : 1.0E-5 EV TO 9.5 EV    
    SINGLE-LEVEL BREIT WIGNER FORMULA WAS ADOPTED.  PARAMETERS    
    WERE DETERMINED ON THE BASIS OF RECOMMENDATION OF MUGHABGHAB  
    /8/.  FOR THE LEVELS WHOSE RADIATIVE WIDTH AND/OR FISSION     
    WIDTH WERE UNKNOWN, AVERAGE GAMMA-G OF 0.043 EV WAS ASSUMED,  
    FISSION WIDTHS WERE CALCULATED FROM (PEAK SIG)*(GAMMA-F).     
    EFFECTIVE SCATTERING RADIUS WAS ASSUMED TO BE 10 FM.          
                                                                  
  2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS                 
                      2200 M/S VALUE       RES. INT.              
        TOTAL           104.09  B            -                    
        ELASTIC           9.928 B            -                    
        FISSION          30.81  B           444 B                 
        CAPTURE          63.34  B          1236 B                 
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  MT=1  TOTAL CROSS SECTION                                       
        ABOVE 9.5 EV, OPTICAL MODEL CALCULATION WAS MADE WITH     
        CASTHY/9/.  THE POTENTIAL PARAMETERS/10/ USED ARE AS      
        FOLLOWS,                                                  
           V = 41.0 - 0.05*EN                      (MEV)          
           WS= 6.4 - 0.15*SQRT(EN)                 (MEV)          
           WV= 0             , VSO = 7.0           (MEV)          
           R = RSO = 1.31    , RS = 1.38            (FM)          
           A = ASO = 0.47    , B  = 0.47            (FM)          
                                                                  
  MT=2  ELASTIC SCATTERING CROSS SECTION                          
        OPTICAL MODEL CALCULATION WAS ADOPTED.                    
                                                                  
  MT=4,51-54,91  INELASTIC SCATTERING CROSS SECTIONS.             
        OPTICAL AND STATISTICAL MODE LCALCULATION WAS MADE WITH   
        CASTHY/9/.  THE LEVEL SCHEME WAS TAKEN FROM REF./11/.     
                   NO         ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0.0        5/2 +               
                    1              0.1        3/2 +               
                    2             20.0        3/2 +               
                    3             29.2        5/2 +               
                    4             42.5        7/2 +               
        LEVELS ABOVE 67 KEV WERE ASSUMED TO BE OVERLAPPING.       
        THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM REF./12/.    
                                                                  
  MT=16,17,37  (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS  
        CALCULATED WITH EVAPORATION MODEL.                        
                                                                  
  MT=18  FISSION CROSS SECTION                                    
        ABOVE 9.5 EV, THE CROSS-SECTION SHAPE WAS ASSUMED TO BE   
        THE SAME AS TH-233 FISSION CROSS SECTION AND IT WAS       
        NORMALIZED BY THE FACTOR OBTAINED FROM SYSTEMATICS OF     
        BEHRENS AND HOWERTON/13/.                                 
                                                                  
  MT=102  CAPTURE CROSS SECTION                                   
        CALCULATED WITH CASTHY. THE GAMMA-RAY STRENGTH FUNCTION   
        WAS ESTIMATED FROM GAMMA-G = 0.040 EV AND LEVEL SPACING = 
        0.53 EV.                                                  
                                                                  
  MT=251  MU-L                                                    
        CALCULATED WITH CASTHY.                                   
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-54,91       CALCULATED WITH OPTICAL MODEL.              
  MT=16,17,18,37      ISOTROPIC IN THE LAB SYSTEM.                
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,37         EVAPORATION SPECTRA WERE GIVEN              
  MT=18               MAXWELLIAN FISSION SPECTRUM.  TEMPERATURE   
                      WAS ESTIMATED FROM Z**2/A VALUES /14/.      
                                                                  
REFERENCES                                                        
 1) TAKAGI N. ET AL.: J. NUCL. SCI. TECHNOL., 27, 853 (1990).     
 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) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL.1, NEUTRON      
    RESONANCE PARAMETERS AND THERMAL CROSS SECTIONS , PART B,     
    Z=61-100", ACADEMIC PRESS (1984).                             
 9) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
10) OHSAWA T. AND OHTA M.: J. NUCL. SCI. TECHNOL., 18, 408 (1981).
11) TOTH K.S.: NUCL. DATA SHEETS, 24, 263 (1978).                 
12) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
13) BEHRENS J.W. AND HOWERTON R.J: NUCL. SCI. ENG., 65, 464(1978).
14) SMITH A.B. ET AL.: ANL/NDM-50 (1979).