91-Pa-232

 91-PA-232 TIT        EVAL-AUG88 N.TAKAGI                         
                      DIST-SEP89 REV2-JUN94                       
----JENDL-3.2         MATERIAL 9134                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
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          1176.23  B            -                    
        ELASTIC          12.23  B            -                    
        FISSION         700.00  B           313 B                 
        CAPTURE         464.00  B           309 B                 
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  MT=1  TOTAL CROSS SECTION                                       
        BELOW 1 EV, CALCULATED AS SUM OF MT'S = 2, 18 AND 102.    
        ABOVE 1 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 1 EV, ASSUMED TO BE THE SAME AS SHAPE ELASTIC       
        SCATTERING CROSS SECTION CALCULATED WITH THE OPTICAL      
        MODEL.  ABOVE 1 EV, 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 RECOMMENDED IN         
        REF./10/.                                                 
                   NO         ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0.0          2 -               
        LEVELS ABOVE 50 KEV 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 700 BARNS WAS TAKEN FROM
        REF./12/, AND 1/V FORM WAS ASSUMED BELOW 1 EV.  FOR       
        ENERGIES ABOVE 1 EV, THE SHAPE WAS ASSUMED TO BE THE SAME 
        AS U-233 FISSION CROSS SECTION AND NORMALIZED TO THE      
        SYSTEMATICS BY BEHRENS AND HOWERTON/13/.                  
                                                                  
  MT=102  CAPTURE CROSS SECTION                                   
        MEASURED THERMAL CROSS SECTION OF 464 BARNS WAS TAKEN FROM
        REF./12/, AND 1/V FORM WAS ASSUMED BELOW 1 EV.  THE CROSS 
        SECTION SHAPE NEAR 1 EV WAS ADJUSTED SO AS TO REPRODUCE   
        THE RESONANCE INTEGRAL/12/.  ABOVE 1 EV, CALCULATED WITH  
        CASTHY. THE GAMMA-RAY STRENGTH FUNCTION WAS ESTIMATED FROM
        GAMMA-GAMMA = 0.040 EV AND LEVEL SPACING = 0.417 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., OHTA M.: J. NUCL. SCI. TECHNOL., 18, 408 (1981).   
10) SCHMORAX M.R.: NUCL. DATA SHEETS, 36, 367 (1982).             
11) GILBERT A., 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., HOWERTON R.J: NUCL. SCI. ENG., 65, 464, (1978). 
14) SMITH A.B. ET AL.: ANL/NDM-50 (1979).