22-Ti- 49

 22-TI- 49 KUR        EVAL-SEP88 K.KOBAYASHI(KUR),H.HASHIKURA(TOK)
                      DIST-SEP89 REV2-NOV93                       
----JENDL-3.2         MATERIAL 2234                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
88-09 COMPILED BY T.ASAMI(NEDAC)                                  
93-12 JENDL-3.2                                                   
       DATA WERE ADOPTED FROM JENDL FUSION FILE.                  
      COMPILED BY T.NAKAGAWA                                      
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      ALL CROSS SECTIONS EXCEPT (3,1), (3,102) AND (3,107)        
      (3,22) NEWLY ADDED.                                         
      ALL ANGULAR DISTRIBUTIONS EXCEPT FOR (4,2).                 
      ALL ENERGY DISTRIBUTIONS.                                   
     ***********************************************************  
     -------------------------------------------------------------
      JENDL FUSION FILE /1/  (AS OF DEC. 1993)                    
            EVALUATED BY K.KOSAKO (NEDAC) AND S. CHIBA (NDC/JAERI)
            COMPILED  BY K.KOSAKO.                                
                                                                  
      -  THE INELASTIC SCATTERING CROSS SECTIONS AND ANGULAR      
         DISTRIBUTIONS OF INELASTICALLY SCATTERED NEUTRONS (EXCEPT
         CONTINUUM INELASTIC) WERE CALCULATED WITH CASTHY2Y AND   
         DWUCKY IN SINCROS-II SYSTEM/2/ INCLUDING CONTRIBUTIONS   
         FROM DIRECT REACTIONS.                                   
      -  THE (N,2N), (N,NA), (N,NP) AND (N,P) REACTION CROSS      
         SECTIONS (MT=16, 22, 28, 103) WERE CALCULATED BY EGNASH2 
         IN THE SINCROS-II.                                       
      -  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE REPLACED 
         BY THOSE CALCULATED BY EGNASH2.  THE DDX'S OF THE        
         CONTINUUM NEUTRONS WERE CALCULATED BY KUMABE'S SYSTEMA-  
         TICS /3/ USING F15TOB /1/.  THE PRECOMPOUND/COMPOUND     
         RATIO WAS CALCULATED BY THE SINCROS- II CODE SYSTEM.     
      -  THE RESONANCE PARAMETERS, TOTAL, CAPTURE AND (N,A) CROSS 
         SECTIONS AND ANG. DISTRIBUTIONS OF ELASTICALLY SCATTERED 
         NEUTRONS WERE TAKEN FROM JENDL-3.1.                      
      -  OPTICAL-MODEL, LEVEL DENSITY AND OTHER PARAMETERS USED IN
         THE SINCROS-II CALCULATION ARE DESCRIBED IN REF./2/.     
         LEVEL SCHEMES WERE DETERMINED ON THE BASIS OF ENSDF/4/.  
     -------------------------------------------------------------
                                                                  
MF=1  GENERAL INFORMATION                                         
 MT=451  DESCRIPTIVE DATA AND DICTIONARY                          
                                                                  
MF=2  RESONANCE PARAMETERS                                        
 MT=151  RESOLVED RESONANCE PARAMETERS                            
   RESOLVED PARAMETERS FOR MLBW FORMULA WERE GIVEN IN THE ENERGY  
   REGION FROM 1.0E-5 EV TO 100 KEV.  PARAMETERS WERE TAKEN FROM  
   REF./5/, FOR POSITIVE RESONANCES.  PARAMETERS FOR NEGATIVE     
   RESONANCE WERE OBTAINED SO THAT THE REPRODUCED CROSS SECTIONS  
   FOR BOTH SCATTERING AND CAPTURE GAVE THE 2200 M/S VALUES OF    
   0.7+-0.3 AND 2.2+-0.3 BARNS, RESPECTIVELY/5/.  THE SCATTERING  
   RADIUS WAS ASSUMED TO BE 4.5 FERMI INSTEAD OF 4.0 FERMI IN     
   REF./5/.  CALCULATED 2200 M/SEC CROSS SECTIONS AND RESONANCE   
   INTEGRALS ARE AS FOLLOWS:                                      
                                                                  
            2200 M/S CROSS SECTION(B)     RES. INTEGRAL(B)        
    ELASTIC        0.69                                           
    CAPTURE        2.21                      1.06                 
    TOTAL          2.90                                           
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  BELOW 100 KEV, NO BACKGROUND CROSS SECTION WAS GIVEN.           
                                                                  
  FOR JENDL-3.2, ALL CROSS-SECTION DATA EXCEPT FOR THE TOTAL,     
  CAPTURE AND (N,A) WERE ADOPTED FROM JENDL FUSION FILE.  THE     
  CALCULATION WAS MADE WITH SINCROS-II SYSTEM/2/ BY ADOPTING      
  WALTER-GUSS OMP MODIFIED BY YAMAMURO/2/ FOR NEUTRON, PEREY OMP  
  /6/ FOR PROTON, LEMOS OMP MODIFIED BY ARTHUR AND YOUNG/7/ FOR   
  ALPHA, LOHR-HAEBERLI OMP/8/ FOR DEUTERON, BECCHETTII-GREENLEES  
  OMP/9/ FOR TRITON AND HE-3, AND STANDARD LEVEL DENSITY          
  PARAMETERS OF SINCROS-II SYSTEM.                                
                                                                  
                                                                  
 MT=1 TOTAL                                                       
   OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH        
   CASTHY CODE/2/. THE OPTICAL POTENTIAL PARAMETERS USED ARE:     
        V = 50.75 - 0.120*EN,    VSO = 4.72   (MEV)               
       WS = 10.9 - 0.234*EN,      WV = 0.0    (MEV)               
        R = 1.26,   RS = 1.02,   RSO = 1.16    (FM)               
        A = 0.52,  ASO = 0.52,     B = 0.40    (FM)               
                                                                  
 MT=2 ELASTIC SCATTERING                                          
   OBTAINED BY SUBTRACTING THE SUM OF THE PARTIAL CROSS SECTIONS  
   FROM THE TOTAL CROSS SECTION.                                  
                                                                  
 MT=4, 51-65, 91 INELASTIC SCATTERING                             
    THE CROSS SECTIONS WERE TAKEN FROM JENDL FUSION FILE.  THE    
    LEVEL SCHEME WAS BASED ON REF./4/  CONTRIBUTIONS OF THE       
    DIRECT PROCESS WERE CALCULATED FOR THE LEVELS MARKED WITH '*'.
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY (DIRECT PROCESS)   
          G.S.      0.0              7/2 -                        
            1       1.3818           3/2 -         *              
            2       1.5421          11/2 -                        
            3       1.586            3/2 -         *              
            4       1.6229           5/2 -                        
            5       1.7235           1/2 -                        
            6       1.762            5/2 -         *              
            7       2.2613           7/2 -         *              
            8       2.4714           7/2 -                        
            9       2.5044           1/2 +         *              
           10       2.5058          15/2 -                        
           11       2.5135           5/2 -                        
           12       2.5174           5/2 +                        
           13       2.6643           3/2 +         *              
           14       2.7201          11/2 -                        
           15       2.7213           3/2 -                        
  LEVELS ABOVE 2.721 MEV WERE ASSUMED TO BE OVERLAPPING.          
                                                                  
 MT=16, 22, 28, 103 (N,2N), (N,NA), (N,NP), (N,P)                 
    ADOPTED FROM JENDL FUSION FILE.  THEORETICAL CALCULATION WAS  
    MADE WITH SINCROS-II.  THE RESULTS WERE NORMALIZED TO         
                                                                  
  (N,NP)+(N,D) 0.00897B AT 14.98 MEV MEASURED BY IKEDA ET AL./10/ 
         (N,P) 0.023  B AT 14.7 MEV MEASURED BY QAIM ET AL./11/   
                                                                  
 MT=102      CAPTURE                                              
    CALCULATED WITH THE CASTHY CODE/12/ AND NORMALIZED TO 22.5 MB 
    AT 30 KEV.                                                    
                                                                  
 MT=107      (N,A)                                                
    CALCULATED WITH THE GNASH CODE/13/.                           
                                                                  
 MT=251      MU-BAR                                               
    CALCULATED WITH OPTICAL MODEL.                                
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
 MT=2                                                             
    CALCULATED WITH THE CASTHY CODE/12/.                          
 MT=16, 22, 28, 51-65, 91                                         
    TAKEN FROM JENDL FUSION FILE.  THE DATA OF MT=16, 22, 28 AND  
    91 WERE TRANSFORMED INTO THE LAB SYSTEM.                      
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
 MT=16, 22, 28, 91                                                
    TAKEN FROM JENDL FUSION FILE.  THE DATA OF MT=16, 22, 28 AND  
    91 WERE TRANSFORMED INTO THE LAB SYSTEM.                      
                                                                  
REFERENCES                                                        
 1) CHIBA, S. ET AL.: JAERI-M 92-027, P.35 (1992).                
 2) YAMAMURO, N.: JAERI-M 90-006 (1990).                          
 3) KUMABE, I. ET AL.: NUCL. SCI. ENG., 104, 280 (1990).          
 4) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE, BNL/NNDC.       
 5) MUGHABGHAB, S.F. ET AL.: " NEUTRON CROSS SECTIONS ", VOL.1,   
    PART A (1981).                                                
 6) PEREY, F.G.: PHYS. REV., 131, 745 (1963).                     
 7) ARTHUR, E.D. AND YOUNG, P.G.: LA-8626-MS (1980).              
 8) LOHR, J.M. AND HAEBERLI W.: NUCL. PHYS., A232, 381 (1974).    
 9) BECCHETTI, F.D. JR. AND GREENLEES G.W.: "POLARIZATION         
   PHENOMENA IN NUCL. REACTIONS," UNIV. WISCONSIN PRESS, P.682    
   (1971).                                                        
10) IKEDA, Y. ET AL.: JAERI 1312 (1988).                          
11) QAIM, S.M. ET AL.: NUCL. PHYS., A283, 269 (1977).             
12) IGARASI, S.  AND FUKAHORI, T.: JAERI 1321 (1991).             
13) YOUNG, P.G. AND ARTHUR, E.D.: LA-6947 (1977).