90-Th-227

 90-TH-227 TIT        EVAL-AUG88 N.TAKAGI                         
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 9025                               
-----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                                                           
88-08 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   RESONANCE PARAMETERS                                   
    NO RESONANCE PARAMETERS WERE GIVEN.                           
                                                                  
  2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS                 
                      2200 M/S VALUE       RES. INT.              
        TOTAL          1749.40  B            -                    
        ELASTIC          12.40  B            -                    
        FISSION         202.00  B           210  B                
        CAPTURE        1535.00  B          1420  B                
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  MT=1  TOTAL CROSS SECTION                                       
        BELOW 0.45 EV, CALCULATED AS SUM OF MT'S = 2, 18 AND 102. 
        ABOVE 0.45 EV, OPTICAL MODEL CALCULATION WAS MADE WITH    
        CASTHY/8/.  THE POTENTIAL PARAMETERS/9/ 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                          
        BELOW 0.45 EV, THE CONSTANT CROSS SECTION OF 12.4 BARNS   
        WAS ASSUMED, WHICH WAS THE SHAPE ELASTIC SCATTERING CROSS 
        SECTION CALCULATED WITH OPTICAL MODEL.  ABOVE THIS ENERGY,
        OPTICAL MODEL CALCULATION WAS ADOPTED.                    
                                                                  
  MT=4, 91  INELASTIC SCATTERING CROSS SECTIONS.                  
        OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH   
        CASTHY/8/.  NO EXCITED LEVELS WERE TAKEN INTO THE         
        CALCULATION.                                              
                   NO         ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0.0         3/2 +              
        LEVELS ABOVE 9.3 KEV/10/ WERE ASSUMED TO BE OVERLAPPING.  
        THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM REF./11/.    
                                                                  
  MT=16,17,37  (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS  
        CALCULATED WITH EVAPORATION MODEL.                        
                                                                  
  MT=18  FISSION CROSS SECTION                                    
        MEASURED THERMAL CROSS SECTION OF 202 BARNS WAS TAKEN FROM
        REF./12/, AND 1/V FORM WAS ASSUMED BELOW 0.45 EV.  IN THE 
        ENERGY RANGE ABOVE 0.45 EV, THE SHAPE WAS ASSUMED TO BE   
        THE SAME AS TH-233 FISSION CROSS SECTION AND IT WAS       
        NORMALIZED TO THE SYSTEMATICS OF BEHRENS AND HOWERTON/13/.
                                                                  
  MT=102  CAPTURE CROSS SECTION                                   
        THE THERMAL CROSS SECTION OF 1535 BARNS WAS ESTIMATED FROM
        THE RATIO OF FISSION AND CAPTURE CROSS SECTIONS AT 1 EV   
        AND THE MEASURED FISSION CROSS SECTION AT 0.0253 EV/12/,  
        AND THE 1/V FORM WAS ASSUMED BELOW 0.45 EV.  ABOVE 0.45   
        EV, CROSS SECTION WAS CALCULATED WITH CASTHY.  THE GAMMA- 
        RAY STRENGTH FUNCTION WAS ESTIMATED FROM GAMMA-GAMMA =    
        0.040 EV AND LEVEL SPACING = 0.9 EV.                      
                                                                  
  MT=251  MU-L                                                    
        CALCULATED WITH CASTHY.                                   
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,91             CALCULATED WITH OPTICAL MODEL.              
  MT=16,17,18,37      ISOTROPIC IN THE LAB SYSTEM.                
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,37,91      EVAPORATION SPECTRA                         
         OBTAINED FROM LEVEL DENSITY PARAMETERS.                  
                                                                  
  MT=18               MAXWELLIAN FISSION SPECTRUM.                
        TEMPERATURE WAS ESTIMATED FROM Z**2/A DEPENDENCE/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) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
 9) OHSAWA T. AND OHTA M.: J. NUCL. SCI. TECHNOL., 18, 408(1981). 
10) MAPLES C.: NUCL. DATA SHEETS, 22, 275 (1977).                 
11) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446(1965). 
12) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL.1, NEUTRON      
    RESONANCE PARAMETERS AND THERMAL CROSS SECTIONS , PART B,     
    Z=61-100", ACADEMIC PRESS (1984).                             
13) BEHRENS J.W. AND HOWERTON R.J: NUCL. SCI. ENG., 65, 464(1978).
14) SMITH A.B. ET AL.: ANL/NDM-50 (1979).