ENTRY 23138 20130518 22352313800000001 SUBENT 23138001 20130518 22352313800100001 BIB 22 164 2313800100002 TITLE Measurement of (n,x n gamma) reactions of interest for 2313800100003 the new nuclear reactors 2313800100004 AUTHOR (M.Kerveno, J.C.Thiry, A.Bacquias, C.Borcea,P.Dessagne,2313800100005 J.C.Drohe,S.Goriely,S.Hilaire, E.Jericha, H.Karam, 2313800100006 A.J.Koning, A.Negret, A.Pavlik, A.Plompen, P.Romain, 2313800100007 C.Rouki, G.Rudolf, M.Stanoiu, N.Nankov, M.Nyman) 2313800100008 INSTITUTE (2ZZZGEL) J.C.Drohe,A.Plompen,C.Rouki,N.Nankov,M.Nyman.2313800100009 (2FR STR) J.C.Thiry, P.Dessagne,H.Karam, M.Kerveno, 2313800100010 G.Rudolf, A.Bacquias. 2313800100011 (2BLGBRU) S.Goriely 2313800100012 (2FR BRC) S.Hilaire, P.Romain 2313800100013 (3RUMBUC) C.Borcea, A.Negret,M.Stanoiu. 2313800100014 (2AUSATI) E.Jericha. 2313800100015 (2NEDNRG) A.J.Koning. 2313800100016 (2AUSVIE) A.Pavlik. 2313800100017 (2GERPTB) Facility to measure efficiency of fission 2313800100018 chamber. 2313800100019 REFERENCE (J,PR/C,87,024609,2013) First author M.Kerveno. 2313800100020 #doi:10.1103/PhysRevC.87.024609 2313800100021 U-235(n,inl) and (n,2n) reaction c-s. 2313800100022 (T,THIRY,20100930) Ph.D.thesis of J.-C.Thiry. 2313800100023 Tables of preliminary results. 2313800100024 (J,EPJ/CS,42,01005,2013) First author M.Kerveno. 2313800100025 #doi:10.1051/epjconf/20134201005 2313800100026 U-235, U-238, Th-232, W-184 prelim.c-s on figures only.2313800100027 (J,KPS,59,1880,2011) ND2010 Conf.Proc. paper #1483; 2313800100028 in ND2010 Abstract book, page 28. 2313800100029 Figures only for U-235, Th-232 . 2313800100030 First author J.C.Thiry. 2313800100031 (C,2010KRAKOW,93,2010) Figures only for U-235,Th-232. 2313800100032 First author M.Kerveno. 2313800100033 (C,2010KRAKOW,121,2010) Details of fission chamber 2313800100034 used for neutron flux measurement. 2313800100035 First author J.C.Thiry. 2313800100036 NEMEA-6 Workshop Proceedings is available online 2313800100037 at web-site www.oecd-nea.org/science/wpec/nemea6 . 2313800100038 EXP-YEAR (2010) 2313800100039 FACILITY (LINAC,2ZZZGEL) GELINA facility FP16/30m. 2313800100040 INC-SOURCE (BRST,PHOTO) Electron beam strikes a depleted uranium 2313800100041 target producing bremsstrahlung and neutrons by 2313800100042 (gamma,xn) and (gamma,F) reactions. 2313800100043 Depleted 52.8 g/cm2 uranium filter very close to the 2313800100044 neutron source is used to reduce the intensity of the 2313800100045 gamma flash. 2313800100046 B-10 filters with a total thickness of 760 mg/cm2 cut 2313800100047 out slow and thermal neutrons, overlapping with 2313800100048 neutrons of the following bursts. 2313800100049 INC-SPECT Pulsed white neutron source GELINA. 2313800100050 Differential neutron flux is on 2313800100051 Fig.2 of J,KPS,58,(1483),2011,Fig.5.3 of T,THIRY,2010,2313800100052 Fig.2 of C,2010KRAKOW,93 , Fig.2 of C,2010KRAKOW,121, 2313800100053 Fig.2 of J,PR/C,87,024609,2013. 2313800100054 Flux was measured using U-235 fission chamber with 2313800100055 a vacuum evaporated U-235-F(4) deposit of U-235 2313800100056 enrichment > 99.5%, and 324. microg/cm**2 thickness 2313800100057 of U-235. 2313800100058 Total beam time for U-235 measurement 1466 hr. 2313800100059 Beam diameter 55 mm. Time resolution 1 ns (FWHM) 2313800100060 SAMPLE U-235: 2313800100061 enrichment (93.20+-0.03)%, total mass 37.43+-0.01 g, 2313800100062 diameter 12.004+-0.004 cm, thickness 0.211+-0.006 mm, 2313800100063 pure U mass 36.2 g, density 15.67g/cm**3, 2313800100064 areal density 0.320+-0.004g/cm**2. 2313800100065 As the beam diameter is only 55 mm, the outer part of 2313800100066 this source has been shielded with lead to reduce 2313800100067 counting rates caused by the natural radioactivity of 2313800100068 uranium. 2313800100069 Surface oxidation was considered for UO(2) and U(3)O(8)2313800100070 cases, UO(2) was chosen in this work. 2313800100071 METHOD (TOF) Flight path 30 meters. 2313800100072 Data acquisition resolution 10 ns. 2313800100073 Neutron energy resolution 1 MeV at 20 MeV. 2313800100074 DETECTOR (HPGE) Four semi-planar n-type high purity germanium 2313800100075 HPGe counters (of Canberra), made 2313800100076 of planar crystals with depths ranging from 2 to 3 cm 2313800100077 and surfaces between 10 and 28 cm2; were optimized for 2313800100078 high resolution detection at low energies (resolution 2313800100079 of 0.7 keV at 122 keV); were placed at angles of 110 2313800100080 and 149 degrees. 2313800100081 Detector Distance to sample Ge diameter Ge thickness2313800100082 mm mm mm 2313800100083 Grey 167.6+-0.5 58.0+-0.2 30.0+-0.2 2313800100084 Red 218.7+-0.5 59.0+-0.2 27.5+-0.2 2313800100085 Green 141.0+-0.5 34.8+-0.2 20.0+-0.2 2313800100086 Blue 134.6+-0.5 35.1+-0.2 19.6+-0.2 2313800100087 Special lead shielding - to eliminate background 2313800100088 radiation. 2313800100089 Eu-152 and Ba-133 sources were used for calibration. 2313800100090 The efficiency of the HPGe detectors was calculated 2313800100091 using a GEANT4 simulation code, which is verified 2313800100092 through measurements with calibrated sources. Also very2313800100093 good agreement with MVNPX code simulation. 2313800100094 (FISCH) The flux was measured by double layer U-235 2313800100095 fission chamber. The deposits, enriched in U-235 2313800100096 (>99.5 %), 324.+-2. microg/cm**2 the vacuum evaporated2313800100097 U-235F(4) layer. 2313800100098 Additional precise calibration measurement was made 2313800100099 at PTB, Braunschweig, at neutron energy 8.4 MeV 2313800100100 leads to exp. efficiency of (94.4+-2.1) %. 2313800100101 PART-DET (G) Identified gamma-energies of U-235 energy spectra 2313800100102 are given in table B.1 of T,THIRY,2010. 2313800100103 EN-SEC (E,G) Energy of gamma transition. 2313800100104 MONITOR (92-U-235(N,F),,SIG) For neutron flux. 2313800100105 MONIT-REF (,,3,ENDF/B-VII.0,,2006) 2313800100106 ANALYSIS (INTAD) Integrated cross section can be obtained in 2313800100107 very good approximation from measurements at only two 2313800100108 angles where the value of the fourth-order Legendre 2313800100109 polynomial P4 is zero, leading to: 2313800100110 SIG=4PI*(0.3479*SIGD(ANG1)+0.6521*SIGD(ANG2), where 2313800100111 SIGD - differential c-s, 2313800100112 ANG1 - 30.6 or 149.4 degree, 2313800100113 ANG2 - 70.1 or 109.9 degree. 2313800100114 ERR-ANALYS (ERR-1,2.3,2.9) Uncertainty of neutron spectrum - 2313800100115 2.9% at high energy, 2.3 in 1-2 MeV neutron energy 2313800100116 region; calculated using 2313800100117 0.3% uncertainty on the areal density of nuclei in 2313800100118 deposit, 2313800100119 2.1 % on fission chamber efficiency, 2313800100120 up to 1 % on fission cross-section from ENDF/B-VII.0, 2313800100121 1.5% on air attenuation coefficient, 2313800100122 < 1% on counting statistics. 2313800100123 (ERR-2) Uncertainty of fission chamber efficiency . 2313800100124 (ERR-3) Uncertainty of areal densities of sample. 2313800100125 (ERR-4) Uncertainty of the uranium layer in the fission2313800100126 chamber. 2313800100127 (MONIT-ERR,0.5,1.) Monitor uncertainty . 2313800100128 (ERR-5) Uncertainty on the self-absorption of the 2313800100129 gamma-rays inside the sample. 2313800100130 (ERR-6,2.,3.) Uncertainty of HPGe detectors efficiency.2313800100131 (ERR-S) Relative statistical uncertainty 2313800100132 (ERR-SYS) Relative systematical uncertainty 2313800100133 MISC-COL (MISC1) Absolute statistical uncertainty 2313800100134 (MISC2) Absolute systematical uncertainty 2313800100135 CORRECTION For dead time of factor from 1.03 to 1.6. 2313800100136 For backgrounds. 2313800100137 For the loss of fission fragments inside the deposit 2313800100138 of ionization chamber. 2313800100139 For back-scattering of the second fission product 2313800100140 into active volume of the chamber. 2313800100141 For the lost due to the application of energy 2313800100142 threshold. 2313800100143 Measured neutron flux was corrected to take into 2313800100144 account the effective neutron yield hitting the sample 2313800100145 (flux was measured 1.56m before the sample) - 1.8 %. 2313800100146 ADD-RES (ANGD) Angular gamma-production cross-sections (b/sr) 2313800100147 for gamma energies of Subents 002-011 are given on 2313800100148 Figures C.1-C.10 of T,THIRY,2010. 2313800100149 (COMP) Compared with TALYS code calculation. 2313800100150 STATUS (COREL,22990001) Th data. 2313800100151 (COREL,23104001) W data. 2313800100152 (COREL,22795001) U-238 data. 2313800100153 HISTORY (20110727C) M.M. 2313800100154 ENTRY was sent 01-08-2011 for approve to 2313800100155 Jean Claude Thiry - jean-claude.thiry@ires.in2p3.fr 2313800100156 (20121018A) NEA DB - DATA in subentries 002-011 2313800100157 deleted at the authors' request. Final data will be 2313800100158 provided after final publication of the results. 2313800100159 (20130518A) M.M. Data were added in Subents 002-005 . 2313800100160 Refs. PR/C,87,024609,2013 and EPJ/CS,42,01005,2013 were2313800100161 added. In AUTHOR list - first author was changed 2313800100162 J.C.Thiry -> M.Kerveno , new names were added. 2313800100163 Subents 006-019 ( for Th ) were moved in Entry 22990. 2313800100164 BIB information was updated according to main reference2313800100165 J,PR/C,87,024609,2013 and comments of Maelle Kerveno. 2313800100166 ENDBIB 164 0 2313800100167 COMMON 4 3 2313800100168 ERR-2 ERR-3 ERR-4 ERR-5 2313800100169 PER-CENT PER-CENT PER-CENT PER-CENT 2313800100170 2.1 1.2 0.6 2. 2313800100171 ENDCOMMON 3 0 2313800100172 ENDSUBENT 171 0 2313800199999 SUBENT 23138002 20130518 22352313800200001 BIB 3 13 2313800200002 REACTION (92-U-235(N,INL)92-U-235,PAR,SIG,G) 2313800200003 Gamma-ray transition cross section for the 129.3 keV 2313800200004 transition 5/2+ -> 7/2- . 2313800200005 REL-REF (D,,W.Younes+,R,UCRL-ID-140313,2000) 2313800200006 In J,PR/C,87,024609,2013 the measured data are compared2313800200007 with W.Younes+,R,UCRL-ID-140313,2000,unpublished. 2313800200008 (A,,H.Karam,T,KARAM,2009) 2313800200009 Agree, considering efficiency difference (in 2313800200010 J.C.Thiry's thesis). 2313800200011 STATUS (TABLE) From author M.Kerveno. 2313800200012 Data are on fig.6 of J,PR/C,87,024609,2013. 2313800200013 Preliminary data in Table C.1 of T,THIRY,2010. 2313800200014 Data are on Fig.3a of C,2010KRAKOW . 2313800200015 ENDBIB 13 0 2313800200016 COMMON 3 3 2313800200017 E LVL-INI LVL-FIN 2313800200018 KEV KEV KEV 2313800200019 129.30 129.30 0. 2313800200020 ENDCOMMON 3 0 2313800200021 DATA 7 26 2313800200022 EN EN-ERR DATA ERR-S ERR-SYS MISC1 2313800200023 MISC2 2313800200024 MEV MEV B PER-CENT PER-CENT B 2313800200025 B 2313800200026 9.39 0.70 0.0175 14.59 2.76 0.0025 2313800200027 0.0005 2313800200028 8.14 0.56 0.0254 8.10 2.75 0.0021 2313800200029 0.0007 2313800200030 7.12 0.46 0.0382 4.82 2.78 0.0018 2313800200031 0.0011 2313800200032 6.29 0.38 0.0597 3.09 2.76 0.0018 2313800200033 0.0016 2313800200034 5.59 0.32 0.0850 2.33 2.76 0.0020 2313800200035 0.0023 2313800200036 4.74 0.50 0.1059 1.60 2.76 0.0017 2313800200037 0.0029 2313800200038 3.89 0.37 0.1134 1.56 2.77 0.0018 2313800200039 0.0031 2313800200040 3.24 0.28 0.1127 1.52 2.77 0.0017 2313800200041 0.0031 2313800200042 2.75 0.22 0.1133 1.49 2.77 0.0017 2313800200043 0.0031 2313800200044 2.36 0.17 0.1053 1.49 2.77 0.0016 2313800200045 0.0029 2313800200046 2.04 0.14 0.1024 1.51 2.77 0.0015 2313800200047 0.0028 2313800200048 1.79 0.12 0.1004 1.51 2.77 0.0015 2313800200049 0.0028 2313800200050 1.58 0.10 0.0994 1.50 2.76 0.0015 2313800200051 0.0027 2313800200052 1.40 0.08 0.1041 1.51 2.77 0.0016 2313800200053 0.0029 2313800200054 1.26 0.07 0.0998 1.54 2.77 0.0015 2313800200055 0.0028 2313800200056 1.13 0.06 0.0977 1.58 2.77 0.0015 2313800200057 0.0027 2313800200058 1.02 0.05 0.1035 1.60 2.77 0.0017 2313800200059 0.0029 2313800200060 0.93 0.04 0.0991 1.62 2.78 0.0016 2313800200061 0.0028 2313800200062 0.81 0.07 0.1162 1.37 2.78 0.0016 2313800200063 0.0032 2313800200064 0.69 0.06 0.1242 1.41 2.77 0.0018 2313800200065 0.0034 2313800200066 0.59 0.04 0.1224 1.50 2.78 0.0018 2313800200067 0.0034 2313800200068 0.51 0.04 0.1159 1.72 2.80 0.0020 2313800200069 0.0032 2313800200070 0.45 0.03 0.1102 2.12 2.80 0.0023 2313800200071 0.0031 2313800200072 0.40 0.02 0.0864 2.64 2.81 0.0023 2313800200073 0.0024 2313800200074 0.35 0.02 0.0797 3.09 2.80 0.0025 2313800200075 0.0022 2313800200076 0.31 0.03 0.0695 3.55 2.79 0.0025 2313800200077 0.0019 2313800200078 ENDDATA 56 0 2313800200079 ENDSUBENT 78 0 2313800299999 SUBENT 23138003 20130518 22352313800300001 BIB 3 18 2313800300002 REACTION (92-U-235(N,2N)92-U-234,PAR,SIG,G) 2313800300003 Gamma-ray transition cross section for the 152.7 keV 2313800300004 transition 6+ -> 4+ of U-234. 2313800300005 REL-REF (D,,A.Hutcheson+,T,HUTCHESON,2008) 2313800300006 Ph.D.thesis, Duke University. 2313800300007 (D,,W.Younes+,R,UCRL-ID-140313,2000) 2313800300008 In J,PR/C,87,024609,2013 the measured data are compared2313800300009 with W.Younes+,R,UCRL-ID-140313,2000,unpublished and 2313800300010 data of A.Hutcheson+. 2313800300011 (A,,H.Karam,T,KARAM,2009) 2313800300012 Agree, considering efficiency difference (in 2313800300013 J.C.Thiry's thesis). 2313800300014 (D,14144001,D.P.McNabb+,C,99SANTA,384,1999) (in 2313800300015 J.C.Thiry'S thesis) 2313800300016 STATUS (TABLE) From author M.Kerveno. 2313800300017 Data are on fig.8 of J,PR/C,87,024609,2013. 2313800300018 Preliminary data in Table C.2 of T,THIRY,2010. 2313800300019 Data are on Fig.3b of C,2010KRAKOW . 2313800300020 ENDBIB 18 0 2313800300021 COMMON 3 3 2313800300022 E LVL-INI LVL-FIN 2313800300023 KEV KEV KEV 2313800300024 152.72 296.071 143.351 2313800300025 ENDCOMMON 3 0 2313800300026 DATA 7 13 2313800300027 EN EN-ERR DATA ERR-S ERR-SYS MISC1 2313800300028 MISC2 2313800300029 MEV MEV B PER-CENT PER-CENT B 2313800300030 B 2313800300031 23.24 2.20 0.0180 54.87 3.03 0.0099 2313800300032 0.0005 2313800300033 19.42 1.67 0.0188 50.44 3.26 0.0095 2313800300034 0.0006 2313800300035 16.47 1.30 0.0269 28.46 2.83 0.0077 2313800300036 0.0008 2313800300037 14.15 1.04 0.0514 11.06 2.81 0.0057 2313800300038 0.0014 2313800300039 12.29 0.84 0.0834 5.37 2.78 0.0045 2313800300040 0.0023 2313800300041 10.78 0.69 0.0904 3.84 2.79 0.0035 2313800300042 0.0025 2313800300043 9.53 0.57 0.0781 3.41 2.77 0.0027 2313800300044 0.0022 2313800300045 8.48 0.48 0.0704 3.17 2.77 0.0022 2313800300046 0.0020 2313800300047 7.60 0.41 0.0604 3.15 2.78 0.0019 2313800300048 0.0017 2313800300049 6.85 0.35 0.0489 3.36 2.78 0.0016 2313800300050 0.0014 2313800300051 6.21 0.30 0.0351 4.31 2.81 0.0015 2313800300052 0.0010 2313800300053 5.65 0.26 0.0120 10.91 3.01 0.0013 2313800300054 0.0004 2313800300055 5.17 0.23 0.0057 19.06 3.10 0.0011 2313800300056 0.0002 2313800300057 ENDDATA 30 0 2313800300058 ENDSUBENT 57 0 2313800399999 SUBENT 23138004 20130518 22352313800400001 BIB 3 12 2313800400002 REACTION (92-U-235(N,2N)92-U-234,PAR,SIG,G) 2313800400003 Gamma-ray transition cross section for the 200.97 keV 2313800400004 transition 8+ -> 6+ of U-234. 2313800400005 REL-REF (D,,W.Younes+,R,UCRL-ID-140313,2000) 2313800400006 In J,PR/C,87,024609,2013 the measured data are compared2313800400007 with W.Younes+,R,UCRL-ID-140313,2000,unpublished. 2313800400008 (D,,H.Karam,T,KARAM,2009) 2313800400009 Data of H.Karam located below (in J.C.Thiry's thesis).2313800400010 STATUS (TABLE) From author M.Kerveno. 2313800400011 Data are on fig.9 of J,PR/C,87,024609,2013. 2313800400012 Preliminary data in Table C.3 of T,THIRY,2010. 2313800400013 Data are on Fig.3c of C,2010KRAKOW . 2313800400014 ENDBIB 12 0 2313800400015 COMMON 3 3 2313800400016 E LVL-INI LVL-FIN 2313800400017 KEV KEV KEV 2313800400018 200.97 497.04 296.07 2313800400019 ENDCOMMON 3 0 2313800400020 DATA 7 11 2313800400021 EN EN-ERR DATA ERR-S ERR-SYS MISC1 2313800400022 MISC2 2313800400023 MEV MEV B PER-CENT PER-CENT B 2313800400024 B 2313800400025 23.30 2.21 0.0032 318.75 4.06 0.0102 2313800400026 0.0001 2313800400027 19.46 1.68 0.0274 27.63 4.15 0.0076 2313800400028 0.0011 2313800400029 16.50 1.31 0.0210 26.69 3.81 0.0056 2313800400030 0.0008 2313800400031 14.18 1.04 0.0209 21.41 3.73 0.0045 2313800400032 0.0008 2313800400033 12.31 0.84 0.0685 9.24 3.13 0.0063 2313800400034 0.0021 2313800400035 10.79 0.69 0.0758 6.29 3.08 0.0048 2313800400036 0.0023 2313800400037 9.54 0.57 0.0578 6.31 3.06 0.0036 2313800400038 0.0018 2313800400039 8.50 0.48 0.0458 6.52 3.05 0.0030 2313800400040 0.0014 2313800400041 7.62 0.41 0.0368 6.76 3.07 0.0025 2313800400042 0.0011 2313800400043 6.86 0.35 0.0205 10.27 3.11 0.0021 2313800400044 0.0006 2313800400045 6.22 0.30 0.0034 55.55 3.16 0.0019 2313800400046 0.0001 2313800400047 ENDDATA 26 0 2313800400048 ENDSUBENT 47 0 2313800499999 SUBENT 23138005 20130518 22352313800500001 BIB 3 16 2313800500002 REACTION (92-U-235(N,2N)92-U-234,PAR,SIG,G) 2313800500003 Gamma-ray transition cross section for the 244.2 keV 2313800500004 transition 10+ -> 8+ of U-234. 2313800500005 REL-REF (D,,A.Hutcheson+,T,HUTCHESON,2008) 2313800500006 Ph.D.thesis, Duke University. 2313800500007 Data of A.Hutcheson are higher of factor about 1.5 2313800500008 (A,,W.Younes+,R,UCRL-ID-140313,2000) 2313800500009 In J,PR/C,87,024609,2013 the measured data are compared2313800500010 with W.Younes+,R,UCRL-ID-140313,2000,unpublished and 2313800500011 data of A.Hutcheson+. 2313800500012 (D,,H.Karam,T,KARAM,2009) 2313800500013 Data of H.Karam located below (in J.C.Thiry's thesis).2313800500014 STATUS (TABLE) From author M.Kerveno. 2313800500015 Data are on fig.10 of J,PR/C,87,024609,2013. 2313800500016 Preliminary data in Table C.4 of T,THIRY,2010. 2313800500017 Data are on Fig.3d of C,2010KRAKOW . 2313800500018 ENDBIB 16 0 2313800500019 COMMON 3 3 2313800500020 E LVL-INI LVL-FIN 2313800500021 KEV KEV KEV 2313800500022 244.2 741.20 497.04 2313800500023 ENDCOMMON 3 0 2313800500024 DATA 7 12 2313800500025 EN EN-ERR DATA ERR-S ERR-SYS MISC1 2313800500026 MISC2 2313800500027 MEV MEV B PER-CENT PER-CENT B 2313800500028 B 2313800500029 23.30 2.21 0.0153 82.52 4.18 0.0126 2313800500030 0.0006 2313800500031 19.46 1.68 0.0064 178.72 3.84 0.0115 2313800500032 0.0002 2313800500033 16.50 1.31 0.0121 69.43 3.44 0.0084 2313800500034 0.0004 2313800500035 14.18 1.04 0.0268 25.11 3.13 0.0067 2313800500036 0.0008 2313800500037 12.31 0.84 0.0467 11.42 3.08 0.0053 2313800500038 0.0014 2313800500039 10.79 0.69 0.0354 11.57 3.11 0.0041 2313800500040 0.0011 2313800500041 9.54 0.57 0.0298 10.69 3.13 0.0032 2313800500042 0.0009 2313800500043 8.50 0.48 0.0171 14.99 3.10 0.0026 2313800500044 0.0005 2313800500045 7.62 0.41 0.0113 19.04 3.25 0.0021 2313800500046 0.0004 2313800500047 6.86 0.35 0.0074 25.14 3.13 0.0019 2313800500048 0.0002 2313800500049 6.22 0.30 0.0015 76.85 3.56 0.0012 2313800500050 0.0001 2313800500051 5.66 0.26 0.0007 179.38 3.56 0.0012 2313800500052 2313800500053 ENDDATA 28 0 2313800500054 ENDSUBENT 53 0 2313800599999 NOSUBENT 23138006 20130518 22352313800600001 NOSUBENT 23138007 20130518 22352313800700001 NOSUBENT 23138008 20130518 22352313800800001 NOSUBENT 23138009 20130518 22352313800900001 NOSUBENT 23138010 20130518 22352313801000001 NOSUBENT 23138011 20130518 22352313801100001 NOSUBENT 23138012 20130518 22352313801200001 NOSUBENT 23138013 20130518 22352313801300001 NOSUBENT 23138014 20130518 22352313801400001 NOSUBENT 23138015 20130518 22352313801500001 NOSUBENT 23138016 20130518 22352313801600001 NOSUBENT 23138017 20130518 22352313801700001 NOSUBENT 23138018 20130518 22352313801800001 NOSUBENT 23138019 20130518 22352313801900001 ENDENTRY 19 0 2313899999999