SUBENT        10868001   20200229                             14641086800100001 
BIB                 12         44                                 1086800100002 
TITLE      Pd-104,105,106,108,110(n,gamma) cross sections above   1086800100003 
           2.6-keV                                                1086800100004 
AUTHOR     (R.L.Macklin,J.Halperin,R.R.Winters)                   1086800100005 
REFERENCE  (J,NSE,71,182,1979)                                    1086800100006 
           (J,NSE,78,110,1981) Corrigendum on corrected average   1086800100007 
           capture cross sections.                                1086800100008 
           (R,ORNL-TM-7058,1979) Preliminary data.                1086800100009 
           (C,79BOLOGN,,103,1979) Data cited in 1981 Corrigendum. 1086800100010 
INSTITUTE  (1USAORL)                                              1086800100011 
FACILITY   (LINAC,1USAORL) Oak Ridge Electron Linear Accelerator, 1086800100012 
           ORELA.                                                 1086800100013 
INC-SOURCE (PHOTO) Pulsed electrons on tantalum with Be-canned    1086800100014 
           water moderator.                                       1086800100015 
METHOD     (TOF) Overlap neutrons eliminated with 0.48-gm/cm2     1086800100016 
           boron-10 filter. Copper and lead shadow bars used to   1086800100017 
           reduce gamma flash and fast neutron flux from source.  1086800100018 
           Data from several samples were combined to derive      1086800100019 
           isotopic cross sections for pure isotopes. Slight      1086800100020 
           revision of neutron flux shape above 70-keV (less      1086800100021 
           than 6%) made referenced to U-235 fission cross        1086800100022 
           sections from ENDF/B-V.                                1086800100023 
DETECTOR   (SCIN) Prompt gammas from capture detected with pair   1086800100024 
           of C(6)F(6) liquid scintillators, 10-cm diameter by 4- 1086800100025 
           cm thick. Beam monitor is Li-6 glass scintillator,     1086800100026 
           0.05-cm thick.                                         1086800100027 
MONITOR    (3-LI-6(N,T)2-HE-4,,SIG) Beam monitor                  1086800100028 
           (92-U-235(N,F),,SIG) from ENDF/B-V                     1086800100029 
CORRECTION Corrected for                                          1086800100030 
            -dead time                                            1086800100031 
            -background                                           1086800100032 
            -environmental effects, approx 48-counts/sec          1086800100033 
            -beam leakage, approx 1-16 percent                    1086800100034 
            -sample scattered neutron effects, 1-3 percent        1086800100035 
STATUS     (APRVD) Approved by R.L.Macklin, 1979/9/7              1086800100036 
HISTORY    (19790521C)                                            1086800100037 
           (19801205A) STATUS comment added.                      1086800100038 
           (19860613A) BIB corrections.                           1086800100039 
           (20170829A) BP: Updated the entry including            1086800100040 
                      uncertainties, added reference. Memo        1086800100041 
                      CP-D/740 incorrectly states that elastic    1086800100042 
                      strength functions are missing, it ignores  1086800100043 
                      subentries 12-16. Added 30 keV cross        1086800100044 
                      sections.                                   1086800100045 
           (20200203U) OS. SAMPLE corr.in subs.3,4                1086800100046 
ENDBIB              44          0                                 1086800100047 
NOCOMMON             0          0                                 1086800100048 
ENDSUBENT           47          0                                 1086800199999 
SUBENT        10868009   20170829                             14351086800900001 
BIB                  5         10                                 1086800900002 
REACTION   (46-PD-106(N,G)46-PD-107,,SIG,,AV)                     1086800900003 
METHOD     Sample yield data linearly combined to derive capture  1086800900004 
           cross sections                                         1086800900005 
CORRECTION Sample yield data corrected for average resonance      1086800900006 
           self-absorption and potential scattering into          1086800900007 
           resonances capture cross section correction factor     1086800900008 
           0.7734 due to error in processing code.                1086800900009 
STATUS     (TABLE) Corrected average cross sections taken from    1086800900010 
           Table II, page 111 of Nuc. Sci. Eng.78,110(9181).      1086800900011 
HISTORY    (19820712A) Data replaced.                             1086800900012 
ENDBIB              10          0                                 1086800900013 
NOCOMMON             0          0                                 1086800900014 
DATA                 3         18                                 1086800900015 
EN-MIN     EN-MAX     DATA                                        1086800900016 
KEV        KEV        MB                                          1086800900017 
         3.         4.      843.1                                 1086800900018 
         4.         6.      671.4                                 1086800900019 
         6.         8.      673.3                                 1086800900020 
         8.        10.      529.5                                 1086800900021 
        10.        15.      413.3                                 1086800900022 
        15.        20.      416.7                                 1086800900023 
        20.        30.      311.9                                 1086800900024 
        30.        40.      256.0                                 1086800900025 
        40.        60.      188.4                                 1086800900026 
        60.        80.      154.3                                 1086800900027 
        80.       100.      132.9                                 1086800900028 
       100.       150.      119.4                                 1086800900029 
       150.       200.      109.3                                 1086800900030 
       200.       300.      108.0                                 1086800900031 
       300.       400.      106.4                                 1086800900032 
       400.       500.      116.3                                 1086800900033 
       500.       600.       95.1                                 1086800900034 
       600.       700.       84.6                                 1086800900035 
ENDDATA             20          0                                 1086800900036 
ENDSUBENT           35          0                                 1086800999999