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)                                
           (J,EPJ/AS,27,129,2006) Preliminary data.               
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.                      
            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        22939008   20100518
BIB                  9         53                                 
REACTION   (52-TE-120(N,G)52-TE-121-G,,SIG,,SPA)                  
SAMPLE      Sample material of natural composition and high       
            elemental purity (>99.5%).                            
              Isotope  Sample material  Rel.abundance (%)         
              Te-120   Te (metal)     0.0927+-0.0009              
           Sample Diameter  Mass          Irr.     Tot.exposure   
                   mm       mg  10**18at  time,min 10**14 n       
           Te-1    10       352.9 1.54     2617     1.96          
           Te-2    10       441.2 1.93     1600     1.52          
           Te-3    8        349.3 1.53     1406     1.56          
           Te-4    8        417.2 1.83     4142     3.03          
           Te-5    8        409.6 1.79     2593     3.09          
            Thin pellets 6 to 10 mm in diameter were pressed from 
            the respective powder or granules and enclosed in thin
            cannings made from 15-microm-thick Al foil. During the
            irradiations the samples were sandwiched between      
            10-30-microm thick gold foils of the same diameter.   
INC-SPECT   Quasi-stellar neutron spectrum approximated by        
            Maxwell-Boltzmann distribution for kT=25.+-0.5 keV.   
            Neutron scattering in Cu backing is negligible.       
            Spectrum is given on Fig.2 of J,PR/C,81,01501,2010.   
            Average neutron intensity at sample position          
            (1.5-3.)*10**9 n/sec.                                 
DECAY-DATA (52-TE-121-G,19.16D,DG,573.1,0.803)                    
            HL=19.16+-0.05 d . Intensity (80.3+-2.5)% .           
DETECTOR   (HPGE) Single high-purity germanium detector with well 
           defined measuring position at 76.0+-0.5 mm from the    
           detector surface was used for counting the activities  
           of the gold foils and of the Te-121, Ba-131, Ba-133m   
           decays.Shielded by 10 cm of lead and 5 mm of copper.   
           Energy and efficiency calibrations have been carried   
           out with a set of reference gamma sources in the energy
           range between 60 and 2000 keV.                         
CORRECTION For self-absorption.                                   
ERR-ANALYS (ERR-1) Uncertainty of detector efficiency.            
           (ERR-2) Uncertainty of divergence of flux.             
           (ERR-3) Uncertainty of Au sample mass.                 
           (ERR-4) Uncertainty of gamma-ray self-absorption.      
           (ERR-5) Uncertainty of gamma-ray intensity for Au.     
           (ERR-6,0.1,1.0) Uncertainty of Au counting statistics. 
           (MONIT-ERR) Uncertainty of gold cross section., not    
           included in final uncertainty.                         
           (ERR-7) Uncertainty of isotopic abundance.             
           (ERR-8) Uncertainty of gamma-ray intensity for Te.     
           (ERR-S,0.4,0.8) Uncertainty of counting statistics.    
           (ERR-T) Total uncertainty including respective         
            uncertainty of gold (2.0%-2.2%).                      
FLAG       (1.) Measurement by sample Te-1                        
           (2.) Measurement by sample Te-2                        
           (3.) Measurement by sample Te-3                        
           (4.) Measurement by sample Te-4                        
           (5.) Measurement by sample Te-5                        
STATUS     (TABLE) Table VII of J,PR/C,81,01501,2010.             
ENDBIB              53          0                                 
COMMON              10          6                                 
KT         KT-ERR     ERR-1      ERR-2      ERR-3      ERR-4      
ERR-5      ERR-7      ERR-8      ERR-T                            
PER-CENT   PER-CENT   PER-CENT   PER-CENT                         
        25.        0.5        2.0        2.0        0.2        0.2
        0.1        0.9        3.1        4.8                      
  ENDCOMMON          6          0                                 
DATA                 3          5                                 
DATA       ERR-T      FLAG                                        
MB         MB         NO-DIM                                      
      474.4       22.9         1.                                 
      465.5       22.4         2.                                 
      484.0       23.2         3.                                 
      462.2       22.3         4.                                 
      468.2       22.7         5.                                 
    ENDDATA          7          0                                 
ENDSUBENT           72          0