ENTRY            22939   20110206
SUBENT    C   22939001   20110206                                 
BIB                 14         48                                 
TITLE      Stellar (n,gamma) cross section of p-process isotopes  
           Part I: Pd-102, Te-120, Ba-130,-132 and Dy-156.        
AUTHOR     (I.Dillmann, C.Domingo-Pardo, M.Heil, F.Kaeppeler,     
           S.Walter, S.Dababneh,T.Rauscher, F.K.Thielemann,R.Plag)
REFERENCE  (J,PR/C,81,015801,2010)                                
           #doi:10.1103/PhysRevC.81.015801                        
           (J,EPJ/AS,27,129,2006) Preliminary data.               
           #doi:10.1140/epja/i2006-08-018-5                       
INSTITUTE  (2GERMUN) I.Dillmann                                   
           (2GERGSI) C.Domingo-Pardo, M.Heil                      
           (2GERKFK) F.Kaeppeler, S.Walter                        
           (2SWTBAS) T.Rauscher, F.K.Thielemann                   
           (3JORJOR) S.Dababneh                                   
              Al Balqa Applied University,Salt 19117,Jordan.      
REL-REF    (R,,J.De Laeter+,J,PAC,75,683,2003)                    
            Isotopic abundances for samples.                      
           (I,,S.Dababneh+,J,NIM/A,517,230,2004)                  
            Details of clover detectors.                          
           (M,,H.Beer+,J,PR/C,21,534,1980) Details of exp.method  
FACILITY   (VDG,2GERKFK) The Karlsruhe 3.7-MV Van de Graaff       
            accelerator operated n DC mode with current of about  
            100 microA (for Li targets) or up to 150 microA for   
            LiF targets.                                          
INC-SOURCE (P-LI7) Neutrons were produced via the Li-7(P,N)Be-7   
            source by bombarding a 30-mum thick layers of metallic
            Li or crystalline LiF on a water-cooled Cu-backings   
            with protons of 1912 keV. Neutrons were emitted into  
            forward cone of 120 deg opening angle.                
METHOD     (ACTIV) Several independent activations were carried   
            out for each isotope with modified exp. parameters.   
           (STTA) Samples were irradiated in close contact with   
            the Li target.                                        
MONITOR    ((MONIT)79-AU-197(N,G)79-AU-198,,SIG) For neutron flux.
MONIT-REF  (,W.Ratynski+,J,PR/C,37,595,1988)                      
DECAY-MON  (79-AU-198,2.69517D,DG,411.8,0.9558)                   
            HL error 0.00021 day, intensity 0.9558+-0.0012.       
DETECTOR   (GLASD) At irradiation the neutron flux was recorded   
           in intervals of 60 or 90sec using a Li-6 glass detector
           91 cm downstream of Li target.                         
ADD-RES     Using the energy dependencies of normalized evaluated 
           cross sections MACS were extrapolated in energy range  
           kT=160-260 keV. Given in Table XVI.                    
HISTORY    (20061220C)  S.M./ M.M.                                
           (20100518A)  M.M. Reference J,PR/C,81 was added.       
            BIB information was updated.                          
            Subents 006-023 were added.                           
           (20110206A) SD: Ref. on Europ.Phys.Jour. A 27,129,2006 
            corrected: EPJ/AS,27,129,2006.                        
ENDBIB              48          0                                 
COMMON               3          3                                 
KT-NRM     MONIT      MONIT-ERR                                   
KEV        MB         MB                                          
        25.       586.         8.                                 
  ENDCOMMON          3          0                                 
ENDSUBENT           55          0                                 
------------------------------------------------------------------------
SUBENT        22939022   20100518
BIB                  6         46                                 
REACTION  1(56-BA-132(N,G)56-BA-133,,SIG,,MXW,DERIV)              
             Derived by ENDF/B-VII.0 .                            
          2(56-BA-132(N,G)56-BA-133,,SIG,,MXW,DERIV)              
             Derived by JEFF-3.0A/3.1 .                           
          3(56-BA-132(N,G)56-BA-133,,SIG,,MXW,DERIV)              
             Derived by JENDL-3.3 .                               
CORRECTION  Correction for the cutoff at 106 keV and small        
            deviations from the shape of ideal Maxwellian spectrum
            by the energy-dependent c-s from data libraries       
            to obtain true Maxwellian average c-s at 25 keV.      
ANALYSIS    Extrapolation of MACS to lower and higher values of kT
            was determined with the evaluated energy-dependent c-s
            from JEFF-3.0A, JEFF-3.1, JENDL-3.3, ENDF-B/VII.0     
            taking into account contribution of RRR, using HF     
            calculation in URR by codes CASTHY, GNASH .           
            Evaluated c-s were folded with experimental neutron   
            spectrum and the ratio of measured c-s to average c-s 
            was calculated - Fnorm:                               
             JEFF-3.0A         0.870                              
             JEFF-3.1          0.869                              
             JENDL-3.3         0.873                              
             ENDF-B/VII.0      0.873                              
           MACS were calculated as:                               
            kT = kT-RRR + Fnorm * kT-URR .         
            Contribution of RRR:                                  
            kT,keV   ENDF-B/VII.0                                 
              5.      1.5                                         
             10.      0.5                                         
             15.      0.3                                         
             20.      0.2                                         
             25.      0.1                                         
             30.      0.1                                         
             40.      0.1                                         
             50.      0.                                          
             60.      0.                                          
             80.      0.                                          
            100.      0.                                          
ERR-ANALYS (ERR-1) Uncertainty of contribution of RRR.            
            Uncertainty of evaluated c-s was not provided,        
            assumed as 0.                                         
           (ERR-T) Quoted total uncertainty includes ERR-1        
            and uncertainty of Fnorm.                             
COMMENT    Of author I.Dillmann. Data of Table XIV are WITHOUT    
           stellar enhancement factors.                           
STATUS     (TABLE) Table XIV of J,PR/C,81,01501,2010.             
           (DEP,22939016)                                         
ENDBIB              46          0                                 
COMMON               1          3                                 
ERR-1                                                             
PER-CENT                                                          
        20.                                                       
  ENDCOMMON          3          0                                 
DATA                 7         11                                 
KT         DATA      1ERR-T     1DATA      2ERR-T     2DATA      3
ERR-T     3                                                       
KEV        MB         MB         MB         MB         MB         
MB                                                                
         5.       929.        35.       915.        35.       915.
        35.                                                       
        10.       641.        24.       637.        24.       637.
        24.                                                       
        15.       530.        20.       528.        20.       528.
        20.                                                       
        20.       468.        18.       467.        18.       467.
        18.                                                       
        25.       427.        16.       426.        16.       426.
        16.                                                       
        30.       398.        15.       397.        15.       397.
        15.                                                       
        40.       358.        14.       357.        14.       357.
        14.                                                       
        50.       331.        13.       331.        13.       331.
        13.                                                       
        60.       313.        12.       312.        12.       312.
        12.                                                       
        80.       290.        11.       290.        11.       290.
        11.                                                       
       100.       277.        11.       276.        11.       276.
        11.                                                       
    ENDDATA         26          0                                 
ENDSUBENT           81          0