ENTRY            14231   20090520                             13541423100000001 
SUBENT        14231001   20090520                             13541423100100001 
BIB                 12         32                                 1423100100002 
TITLE      Neutron inelastic scattering and reactions in          1423100100003 
           natural Pb as a background in neutrinoless             1423100100004 
           double-beta-decay experiments                          1423100100005 
AUTHOR     (V.E.Guiseppe,M.Devlin,S.R.Elliott,N.Fotiades,A.Hime,  1423100100006 
           D.-M.Mei, R.O.Nelson,D.V.Perepelitsa)                  1423100100007 
INSTITUTE  (1USALAS)                                              1423100100008 
           (1USAUSA) University of South Dakota, Vermillion,      1423100100009 
           South Dakota                                           1423100100010 
REFERENCE  (J,PR/C,79,054604,2009)                                1423100100011 
FACILITY   (LINAC,1USALAS)Data were collected at the Los Alamos   1423100100012 
           Neutron Science Center (LANSCE) Weapons Neutron        1423100100013 
           Research (WNR) facility, which provides neutrons in    1423100100014 
           the energy range from 0.2 - 800 MeV                    1423100100015 
SAMPLE     Five stacked foils of natural Pb (natPb) angled 20 deg 1423100100016 
           off the normal of the beam direction. Each foil        1423100100017 
           measured nominally 5 cm x 5 cm in area and 0.475 mm    1423100100018 
           in thickness. Sample was located at the center of      1423100100019 
           gamma ray detector array.                              1423100100020 
DETECTOR   (HPGE)The GEANIE spectrometer consists of 26 HPGe      1423100100021 
           detectors, 20 of which haveBGO active shields. Of      1423100100022 
           the 26 Ge detectors, 16 are coaxial geometry with a    1423100100023 
           dynamic range up to 4 MeV and 10 are planar geometry   1423100100024 
           detectors with a limited dynamic range of 1 MeV.       1423100100025 
           Only coaxial detectors were used in the experiment.    1423100100026 
METHOD     (TOF) Time of flight method was used for neutron       1423100100027 
           energy determination                                   1423100100028 
INC-SOURCE (SPALL)                                                1423100100029 
MONITOR    (92-U-235(N,F),,SIG)                                   1423100100030 
           (92-U-238(N,F),,SIG)                                   1423100100031 
ERR-ANALYS (ERR-S) Statistical uncertainty                        1423100100032 
           (ERR-SYS) Systematic uncertainty                       1423100100033 
HISTORY    (20090520C) Compiled by S.H.                           1423100100034 
ENDBIB              32          0                                 1423100100035 
NOCOMMON             0          0                                 1423100100036 
ENDSUBENT           35          0                                 1423100199999 
SUBENT        14231002   20090520                             13541423100200001 
BIB                  2          2                                 1423100200002 
REACTION   (82-PB-0(N,X)82-PB-206,PAR,SIG,G,AV)                   1423100200003 
STATUS     (TABLE) Data taken from tab. 1 of the reference        1423100200004 
ENDBIB               2          0                                 1423100200005 
COMMON               1          3                                 1423100200006 
E                                                                 1423100200007 
KEV                                                               1423100200008 
2041.0                                                            1423100200009 
ENDCOMMON            3          0                                 1423100200010 
DATA                 5          5                                 1423100200011 
EN-MIN     EN-MAX     DATA       ERR-S      ERR-SYS               1423100200012 
MEV        MEV        MB         MB         MB                    1423100200013 
 2.87        4.20     0.72       0.44       0.07                  1423100200014 
 4.20        6.72     4.0        0.6        0.4                   1423100200015 
 6.72       12.50     3.6        0.7        0.3                   1423100200016 
12.50       31.15     3.3        0.6        0.3                   1423100200017 
31.15      200.00     0.50       0.17       0.05                  1423100200018 
ENDDATA              7          0                                 1423100200019 
ENDSUBENT           18          0                                 1423100299999 
SUBENT        14231003   20090520                             13541423100300001 
BIB                  2          3                                 1423100300002 
REACTION   ((82-PB-0(N,X)82-PB-207,PAR,SIG,G,AV)+                 1423100300003 
           (82-PB-0(N,X)82-PB-208,PAR,SIG,G,AV))                  1423100300004 
STATUS     (TABLE) Data taken from tab. 1 of the reference        1423100300005 
ENDBIB               3          0                                 1423100300006 
COMMON               2          3                                 1423100300007 
E          E                                                      1423100300008 
KEV        KEV                                                    1423100300009 
3061.0     3062.0                                                 1423100300010 
ENDCOMMON            3          0                                 1423100300011 
DATA                 6          5                                 1423100300012 
EN-MIN     EN-MAX     DATA       ERR-S      ERR-SYS    DATA-MAX   1423100300013 
MEV        MEV        MB         MB         MB         MB         1423100300014 
 2.87        4.20                                      0.3        1423100300015 
 4.20        6.72     3.0        0.5        0.3                   1423100300016 
 6.72       12.50     3.9        0.8        0.4                   1423100300017 
12.50       31.15                                      0.4        1423100300018 
31.15      200.00                                      0.2        1423100300019 
ENDDATA              7          0                                 1423100300020 
ENDSUBENT           19          0                                 1423100399999 
ENDENTRY             3          0                                 1423199999999