22-Ti- 50

 22-TI- 50 KUR        EVAL-SEP88 K.KOBAYASHI(KUR),HASHIKURA(TOK)  
                      DIST-SEP89 REV2-NOV93                       
----JENDL-3.2         MATERIAL 2237                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
88-09  COMPILED BY T.ASAMI(NEDAC)                                 
93-11 JENDL-3.2                                                   
       DATA WERE MAINLY ADOPTED FROM JENDL FUSION FILE.           
      COMPILED BY T.NAKAGAWA                                      
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      ALL CROSS SECTIONS EXCEPT (3,1) AND (3,102)                 
      ALL ANGULAR DISTRIBUTIONS EXCEPT FOR (4,2).                 
      ALL ENERGY DISTRIBUTIONS.                                   
     ***********************************************************  
     -------------------------------------------------------------
      JENDL FUSION FILE /1/  (AS OF NOV. 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), (N,P) AND (N,A) REACTION     
         CROSS SECTIONS (MT=16, 22, 28, 103, 107) 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 AND CAPTURE 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 200 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 VALUE OF     
   3.7+-0.3 AND 0.179+-0.003 BARNS, RESPECTIVELY/5/.  THE         
   SCATTERING RADIUS WAS ASSUMED TO BE 4.5 FERMI.  CALCULATED 2200
   M/SEC CROSS SECTIONS AND RESONANCE INTEGRALS ARE AS FOLLOWS:   
                                                                  
            2200 M/S CROSS SECTION(B)     RES. INTEGRAL(B)        
    ELASTIC        3.71                                           
    CAPTURE        0.18                     0.086                 
    TOTAL          3.88                                           
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  BELOW 180 KEV, NO BACKGROUND CROSS SECTION WAS GIVEN.           
                                                                  
  FOR JENDL-3.2, ALL CROSS-SECTION DATA EXCEPT FOR THE TOTAL AND  
  CAPTURE 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/10/. 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, 51-61, 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 '*', 
   USING DEFORMATION PARAMETERS COMPILED BY RAMAN ET AL./11/ AND  
   SPEAR/12/.                                                     
                                                                  
           NO.      ENERGY(MEV)    SPIN-PARITY (DIRECT PROCESS)   
          G.S.      0.0                0 +                        
            1       1.5538             2 +         *              
            2       2.6749             4 +         *              
            3       3.1987             6 +         *              
            4       3.771              2 +                        
            5       3.8681             0 +                        
            6       3.9748             4 +                        
            7       4.1473             4 +         *              
            8       4.1718             3 +                        
            9       4.1723             2 +         *              
           10       4.311              2 +         *              
           11       4.4105             3 -         *              
  LEVELS ABOVE 4.411 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,2N) 1.0    B AT 14.9 MEV (SYSTEMATICS BY KASUGAI/13/), 
         (N,P) 0.0134 B AT 14.94 MEV MEASURED BY IKEDA ET AL./14/,
         (N,A) 0.0104 B AT 14.95 MEV MEASURED BY IKEDA ET AL./14/.
                                                                  
 MT=102      CAPTURE                                              
    CALCULATED WITH THE CASTHY CODE/10/ AND NORMALIZED TO 2.3 MB  
    AT 25 KEV.                                                    
                                                                  
 MT=251      MU-BAR                                               
    CALCULATED BASED ON OPTICAL MODEL                             
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
 MT=2                                                             
    CALCULATED WITH THE CASTHY CODE/10/.                          
 MT=16, 22, 28, 51-61, 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) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).              
11) RAMAN, S., ET AL.: ATOM. DATA AND NUCL. DATA TABLES 36, 1     
    (1987)                                                        
12) SPEAR, R.H.: ATOM. DATA AND NUCL. DATA TABLE, 42, 55 (1989).  
13) KASUGAI Y.: PRIVATE COMMUNICATION (1993).                     
14) IKEDA, Y. ET AL.: JAERI 1312 (1988).