ENTRY 22990 20130920 22352299000000001 SUBENT 22990001 20130920 22352299000100001 BIB 19 142 2299000100002 TITLE (n,xn gamma) reaction cross section measurements for 2299000100003 (n,xn) reaction studies. 2299000100004 AUTHOR (M.Kerveno, J.C.Thiry, A.Bacquias, C.Borcea,P.Dessagne,2299000100005 J.C.Drohe,N.Nankov,M.Nyman,A.Negret,A.Plompen,C.Rouki, 2299000100006 G.Rudolf,M.Stanoiu, E.Jericha, H.Karam, A.J.Koning, 2299000100007 A.Pavlik) 2299000100008 INSTITUTE (2ZZZGEL) J.C.Drohe,A.Plompen,C.Rouki,N.Nankov,M.Nyman 2299000100009 (2FR STR) J.C.Thiry, P.Dessagne,H.Karam, M.Kerveno, 2299000100010 G.Rudolf, M.Stanoiu, A.Bacquias. 2299000100011 (3RUMBUC) C.Borcea, A.Negret. 2299000100012 (2AUSATI) E.Jericha. 2299000100013 (2NEDNRG) A.J.Koning. 2299000100014 (2AUSVIE) A.Pavlik. 2299000100015 (2GERPTB) Facility to measure efficiency of fission 2299000100016 chamber. 2299000100017 REFERENCE (J,EPJ/CS,42,01005,2013) First author M.Kerveno. 2299000100018 #doi:10.1051/epjconf/20134201005 2299000100019 U-235, U-238, Th-232, W-184 prelim.c-s on figures only.2299000100020 (T,THIRY,20100930) Ph.D.thesis of J.-C.Thiry. 2299000100021 Tables of preliminary results for U-235,Th-232. 2299000100022 (J,KPS,59,1880,2011) ND2010 Conf.Proc. paper #1483; 2299000100023 in ND2010 Abstract book, page 28. 2299000100024 Figures only for U-235, Th-232 . 2299000100025 First author J.C.Thiry. 2299000100026 (C,2010KRAKOW,93,2010) Figures only for U-235,Th-232. 2299000100027 First author M.Kerveno. 2299000100028 (C,2010KRAKOW,121,2010) Details of fission chamber 2299000100029 used for neutron flux measurement. 2299000100030 NEMEA-6 Workshop Proceedings is available online 2299000100031 at web-site www.oecd-nea.org/science/wpec/nemea6 . 2299000100032 FACILITY (LINAC,2ZZZGEL) GELINA facility FP16/30m. 2299000100033 INC-SOURCE (BRST,PHOTO) Electron beam strikes a depleted uranium 2299000100034 target producing bremsstrahlung and neutrons by 2299000100035 (gamma,xn) and (gamma,F) reactions. 2299000100036 INC-SPECT Pulsed white neutron source GELINA. 2299000100037 Differential neutron flux is on Fig.2 of 2299000100038 J,KPS,58,(1483),2011 , Fig.5.3 of T,THIRY,2010, 2299000100039 Fig.2 of C,2010KRAKOW,93 , Fig.2 of C,2010KRAKOW,121. 2299000100040 Flux was measured using U-235 fission chamber with 2299000100041 a vacuum evaporated U-235-F(4) deposit of U-235 2299000100042 enrichment > 99.5%, and 324. microg/cm**2 thickness 2299000100043 of U-235. 2299000100044 SAMPLE U-235: 2299000100045 purity 93.18%, atomic mass 235.043923 g/mol,total mass 2299000100046 37.43+-0.01 g, surface 113.173 cm**2, thickness 2299000100047 0.211+-0.006 mm, density 15.67 g/cm**3, areal density 2299000100048 0.330+-0.009 g/cm**2 . 2299000100049 Th-232: 2299000100050 purity 99.5%, atomic mass 232.038050 g/mol,total mass 2299000100051 11.9939+-0.0001 g, surface 36.463 cm**2, thickness 2299000100052 0.302+-0.004 mm, density 10.894 g/cm**3, areal density 2299000100053 0.329-0.004 g/cm**2 2299000100054 METHOD (TOF) Flight path 30 meters. Time resolution 10 ns. 2299000100055 Neutron energy resolution 0.86 MeV at 20 MeV, 0.3 keV 2299000100056 at 100 keV neutron energy. Exact sample distance 2299000100057 28.817+-0.001 m. 2299000100058 DETECTOR (HPGE) Four semi-planar n-type high purity germanium 2299000100059 HPGe counters (of Canberra), made 2299000100060 of planar crystals with depths ranging from 2 to 3 cm 2299000100061 and surfaces between 10 and 28 cm2; were optimized for 2299000100062 high resolution detection at low energies (resolution 2299000100063 of 0.7 keV at 122 keV); were placed at angles of 110 2299000100064 and 149 degrees, placed at distances 167.6, 218.7, 2299000100065 141.0, 134.6 mm from sample. 2299000100066 Special lead shielding - to eliminate background 2299000100067 radiation. 2299000100068 Eu-152 sources of 2 and 50 mm diameter and Ba-133 point2299000100069 source were used for calibration. Geant4 code 2299000100070 simulations were compared with measured gamma-emission.2299000100071 (FISCH) The flux was measured by double layer U-235 2299000100072 fission chamber. The deposits, enriched in U-235 2299000100073 (>99.5 %), 2299000100074 1) 323.757+-1.740 microg/cm**2 , the vacuum evaporated 2299000100075 U-235F(4) layer, 6.7 g/cm**3, 7.00 cm diameter, 2299000100076 38.48 cm**2 surface, 639.52 nm thickness,12.46 microg 2299000100077 U mass, 8.2978E17 at/cm**2, position 27.2601 m; 2299000100078 2) 387+-3 microg/cm**2, the spray painted U-235(3)O(8) 2299000100079 layer, position 27.4151m, 8.38 g/cm**3, 10.16 cm 2299000100080 diameter, 81.07 cm**2 surface, 545.7 nm thickness, 2299000100081 31.38 mg U mass, 9.919E17 at/cm**2. 2299000100082 Located at 27.260 m flight distance. 2299000100083 Operated at gas pressure 1 atm. 2299000100084 Additional precise calibration measurement was made 2299000100085 at PTB, Braunschweig, at neutron energy 8.39+-0.04 MeV 2299000100086 using fission c-s 1.793+-0.014 b from interpolation of 2299000100087 ENDF/B-VII.0 data, leads to exp. efficiency of 2299000100088 (94.4+-2.1) %. 2299000100089 Only UF4 deposit was used for the flux determination. 2299000100090 DECAY-DATA (63-EU-152,13.51YR) 13.51+-0.03 yr. 2299000100091 Eu-152 data used in analysis of HPGE efficiency 2299000100092 uncertainty determination: 2299000100093 Gamma energy,keV Branching ratio Error on emitted 2299000100094 particles 2299000100095 45.4+46.6 14.95+-0.47 3.22 % 2299000100096 121.78 28.48+-0.13 0.85 % 2299000100097 244.70 7.53+-0.04 0.90 % 2299000100098 344.28 26.57+-0.11 0.83 % 2299000100099 443.97 3.13+-0.01 0.89 % 2299000100100 778.90 12.98+-0.06 0.88 % 2299000100101 964.06 14.64+-0.06 0.85 % 2299000100102 1085.84 11.87+-0.05 0.87 % 2299000100103 PART-DET (G) Identified gamma-energies of U-235 energy spectra 2299000100104 are given in table B.1 of T,THIRY,2010; 2299000100105 of Th-232 - in Table B.2 . 2299000100106 MONITOR (92-U-235(N,F),,SIG) For neutron flux. 2299000100107 MONIT-REF (,,3,ENDF/B-VII.0,,2006) 2299000100108 ERR-ANALYS (ERR-1,2.3,2.9) Uncertainty of neutron spectrum - 2299000100109 2.9% at high energy, 2.3 in 1-2 MeV neutron energy 2299000100110 region; calculated using 2299000100111 0.3% uncertainty on the areal density of nuclei in 2299000100112 deposit, 2299000100113 2.1 % on fission chamber efficiency, 2299000100114 up to 1 % on fission cross-section from ENDF/B-VII.0, 2299000100115 1.5% on air attenuation coefficient, 2299000100116 < 1% on counting statistics. 2299000100117 (ERR-2) Uncertainty of fission chamber efficiency . 2299000100118 CORRECTION For dead time of factor from 1.03 to 1.6. 2299000100119 For backgrounds. 2299000100120 For the loss of fission fragments inside the deposit 2299000100121 of ionization chamber. 2299000100122 For back-scattering of the second fission product 2299000100123 into active volume of the chamber. 2299000100124 For the lost due to the application of energy 2299000100125 threshold. 2299000100126 Measured neutron flux was corrected to take into 2299000100127 account the effective neutron yield hitting the sample 2299000100128 (flux was measured 1.56m before the sample) - 1.8 %. 2299000100129 ADD-RES (ANGD) Angular gamma-production cross-sections (b/sr) 2299000100130 fro gamma energies of Subents 002-011 are given on 2299000100131 Figures C.1-C.10 of T,THIRY,2010. 2299000100132 STATUS (COREL,23138001) Data for U-235. 2299000100133 (COREL,23104001) Data for W. 2299000100134 (COREL,22795001) U-238 data. 2299000100135 HISTORY (20110727C) M.M. 2299000100136 ENTRY was sent 01-08-2011 for approve to 2299000100137 Jean Claude Thiry - jean-claude.thiry@ires.in2p3.fr 2299000100138 (20121018A) NEA DB - DATA in subentries were 2299000100139 deleted at the authors' request. Final data will be 2299000100140 provided after final publication of the results. 2299000100141 (20130920T) M.M. Data for Th, Subents 006-019 from 2299000100142 Entry 23138 were moved in this Entry 22990, Subents 2299000100143 002-015, respectively . 2299000100144 ENDBIB 142 0 2299000100145 COMMON 1 3 2299000100146 ERR-2 2299000100147 PER-CENT 2299000100148 2.1 2299000100149 ENDCOMMON 3 0 2299000100150 ENDSUBENT 149 0 2299000199999 SUBENT 22990002 20130920 22352299000200001 BIB 6 10 2299000200002 REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299000200003 Gamma-ray transition cross section for the 112.75 keV 2299000200004 transition 4+ -> 2+ of Th-232. 2299000200005 CORRECTION For dead time- using 238.6 keV gamma-ray by decay of 2299000200006 Bi-212. 2299000200007 COMMENT The data has been acquired within 375 hours. 2299000200008 EN-SEC (E,G) Energy of gamma transition. 2299000200009 ADD-RES (COMP) Compared with TALYS code calculation. 2299000200010 STATUS (PRELM) Table C.5 of T,THIRY,2010. 2299000200011 Data are on Fig.6 right of C,2010KRAKOW . 2299000200012 ENDBIB 10 0 2299000200013 COMMON 3 3 2299000200014 E LVL-INI LVL-FIN 2299000200015 KEV KEV KEV 2299000200016 112.75 162.12 49.37 2299000200017 ENDCOMMON 3 0 2299000200018 NODATA 0 0 2299000200019 ENDSUBENT 18 0 2299000299999 SUBENT 22990003 20130920 22352299000300001 BIB 6 10 2299000300002 REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299000300003 Gamma-ray transition cross section for the 171.2 keV 2299000300004 transition 6+ -> 4+ of Th-232. 2299000300005 CORRECTION For dead time- using 238.6 keV gamma-ray by decay of 2299000300006 Bi-212. 2299000300007 COMMENT The data has been acquired within 375 hours. 2299000300008 EN-SEC (E,G) Energy of gamma transition. 2299000300009 ADD-RES (COMP) Compared with TALYS code calculation. 2299000300010 STATUS (PRELM) Table C.6 of T,THIRY,2010. 2299000300011 Data are on Fig.6 right of C,2010KRAKOW . 2299000300012 ENDBIB 10 0 2299000300013 COMMON 3 3 2299000300014 E LVL-INI LVL-FIN 2299000300015 KEV KEV KEV 2299000300016 171.2 333.3 162.1 2299000300017 ENDCOMMON 3 0 2299000300018 NODATA 0 0 2299000300019 ENDSUBENT 18 0 2299000399999 SUBENT 22990004 20130920 22352299000400001 BIB 6 10 2299000400002 REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299000400003 Gamma-ray transition cross section for the 223.6 keV 2299000400004 transition 8+ -> 6+ of Th-232. 2299000400005 CORRECTION For dead time- using 238.6 keV gamma-ray by decay of 2299000400006 Bi-212. 2299000400007 COMMENT The data has been acquired within 375 hours. 2299000400008 EN-SEC (E,G) Energy of gamma transition. 2299000400009 ADD-RES (COMP) Compared with TALYS code calculation. 2299000400010 STATUS (PRELM) Table C.7 of T,THIRY,2010. 2299000400011 Data are on Fig.6 right of C,2010KRAKOW . 2299000400012 ENDBIB 10 0 2299000400013 COMMON 3 3 2299000400014 E LVL-INI LVL-FIN 2299000400015 KEV KEV KEV 2299000400016 223.6 556.9 333.3 2299000400017 ENDCOMMON 3 0 2299000400018 NODATA 0 0 2299000400019 ENDSUBENT 18 0 2299000499999 SUBENT 22990005 20130920 22352299000500001 BIB 6 10 2299000500002 REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299000500003 Gamma-ray transition cross section for the 49.37 keV 2299000500004 transition 2+ -> 0+ of Th-232. 2299000500005 CORRECTION For dead time- using 238.6 keV gamma-ray by decay of 2299000500006 Bi-212. 2299000500007 COMMENT The data has been acquired within 375 hours. 2299000500008 EN-SEC (E,G) Energy of gamma transition. 2299000500009 ADD-RES (COMP) Compared with TALYS code calculation. 2299000500010 STATUS (PRELM) Table C.8 of T,THIRY,2010. 2299000500011 Data are on Fig.6 left of C,2010KRAKOW . 2299000500012 ENDBIB 10 0 2299000500013 COMMON 3 3 2299000500014 E LVL-INI LVL-FIN 2299000500015 KEV KEV KEV 2299000500016 49.37 49.37 0. 2299000500017 ENDCOMMON 3 0 2299000500018 NODATA 0 0 2299000500019 ENDSUBENT 18 0 2299000599999 SUBENT 22990006 20130920 22352299000600001 BIB 6 10 2299000600002 REACTION (90-TH-232(N,2N)90-TH-231,PAR,SIG,G) 2299000600003 Gamma-ray transition cross section for the 185.7 keV 2299000600004 transition 5/2- -> 5/2+ of Th-231. 2299000600005 CORRECTION For dead time- using 238.6 keV gamma-ray by decay of 2299000600006 Bi-212. 2299000600007 COMMENT The data has been acquired within 375 hours. 2299000600008 EN-SEC (E,G) Energy of gamma transition. 2299000600009 ADD-RES (COMP) Compared with TALYS code calculation. 2299000600010 STATUS (PRELM) Table C.9 of T,THIRY,2010. 2299000600011 Data are on Fig.8 left of C,2010KRAKOW . 2299000600012 ENDBIB 10 0 2299000600013 COMMON 3 3 2299000600014 E LVL-INI LVL-FIN 2299000600015 KEV KEV KEV 2299000600016 185.7 185.7 0. 2299000600017 ENDCOMMON 3 0 2299000600018 NODATA 0 0 2299000600019 ENDSUBENT 18 0 2299000699999 SUBENT 22990007 20130920 22352299000700001 BIB 6 10 2299000700002 REACTION (90-TH-232(N,3N)90-TH-230,PAR,SIG,G) 2299000700003 Gamma-ray transition cross section for the 182.5 keV 2299000700004 transition 6+ -> 4+ of Th-230. 2299000700005 CORRECTION For dead time- using 238.6 keV gamma-ray by decay of 2299000700006 Bi-212. 2299000700007 COMMENT The data has been acquired within 375 hours. 2299000700008 EN-SEC (E,G) Energy of gamma transition. 2299000700009 ADD-RES (COMP) Compared with TALYS code calculation. 2299000700010 STATUS (PRELM) Table C.10 of T,THIRY,2010. 2299000700011 Data are on Fig.8 right of C,2011KRAKOW . 2299000700012 ENDBIB 10 0 2299000700013 COMMON 3 3 2299000700014 E LVL-INI LVL-FIN 2299000700015 KEV KEV KEV 2299000700016 182.5 356.5 174.10 2299000700017 ENDCOMMON 3 0 2299000700018 NODATA 0 0 2299000700019 ENDSUBENT 18 0 2299000799999 SUBENT 22990008 20130920 22352299000800001 BIB 4 7 2299000800002 REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299000800003 Gamma-ray transition cross section for the 550.4 keV 2299000800004 transition L13 -> L3 of Th-232. 2299000800005 EN-SEC (E,G) Energy of gamma transition. 2299000800006 ADD-RES (COMP) Compared with TALYS code calculation. 2299000800007 STATUS (PRELM) Preliminary data. 2299000800008 Data are on Fig.7 left top of C,2011KRAKOW . 2299000800009 ENDBIB 7 0 2299000800010 COMMON 1 3 2299000800011 E 2299000800012 KEV 2299000800013 550.4 2299000800014 ENDCOMMON 3 0 2299000800015 NODATA 0 0 2299000800016 ENDSUBENT 15 0 2299000899999 SUBENT 22990009 20130920 22352299000900001 BIB 4 7 2299000900002 REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299000900003 Gamma-ray transition cross section for the 611.8 keV 2299000900004 transition L8 -> L2 of Th-232. 2299000900005 EN-SEC (E,G) Energy of gamma transition. 2299000900006 ADD-RES (COMP) Compared with TALYS code calculation. 2299000900007 STATUS (PRELM) Preliminary data. 2299000900008 Data are on Fig.7 middle top of C,2011KRAKOW . 2299000900009 ENDBIB 7 0 2299000900010 COMMON 1 3 2299000900011 E 2299000900012 KEV 2299000900013 611.8 2299000900014 ENDCOMMON 3 0 2299000900015 NODATA 0 0 2299000900016 ENDSUBENT 15 0 2299000999999 SUBENT 22990010 20130920 22352299001000001 BIB 4 7 2299001000002 REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299001000003 Gamma-ray transition cross section for the 665.0 keV 2299001000004 transition L5 -> L1 of Th-232. 2299001000005 EN-SEC (E,G) Energy of gamma transition. 2299001000006 ADD-RES (COMP) Compared with TALYS code calculation. 2299001000007 STATUS (PRELM) Preliminary data. 2299001000008 Data are on Fig.7 right top of C,2011KRAKOW . 2299001000009 ENDBIB 7 0 2299001000010 COMMON 1 3 2299001000011 E 2299001000012 KEV 2299001000013 665.0 2299001000014 ENDCOMMON 3 0 2299001000015 NODATA 0 0 2299001000016 ENDSUBENT 15 0 2299001099999 SUBENT 22990011 20130920 22352299001100001 BIB 4 7 2299001100002 REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299001100003 Gamma-ray transition cross section for the 714.2 keV 2299001100004 transition L5 -> L0 of Th-232. 2299001100005 EN-SEC (E,G) Energy of gamma transition. 2299001100006 ADD-RES (COMP) Compared with TALYS code calculation. 2299001100007 STATUS (PRELM) Preliminary data. 2299001100008 Data are on Fig.7 left bottom of C,2011KRAKOW . 2299001100009 ENDBIB 7 0 2299001100010 COMMON 2 3 2299001100011 E LVL-FIN 2299001100012 KEV KEV 2299001100013 714.2 0. 2299001100014 ENDCOMMON 3 0 2299001100015 NODATA 0 0 2299001100016 ENDSUBENT 15 0 2299001199999 SUBENT 22990012 20130920 22352299001200001 BIB 4 7 2299001200002 REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299001200003 Gamma-ray transition cross section for the 735.9 keV 2299001200004 transition L9 -> L1 of Th-232. 2299001200005 EN-SEC (E,G) Energy of gamma transition. 2299001200006 ADD-RES (COMP) Compared with TALYS code calculation. 2299001200007 STATUS (PRELM) Preliminary data. 2299001200008 Data are on Fig.7 middle bottom of C,2011KRAKOW . 2299001200009 ENDBIB 7 0 2299001200010 COMMON 1 3 2299001200011 E 2299001200012 KEV 2299001200013 735.9 2299001200014 ENDCOMMON 3 0 2299001200015 NODATA 0 0 2299001200016 ENDSUBENT 15 0 2299001299999 SUBENT 22990013 20130920 22352299001300001 BIB 4 7 2299001300002 REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299001300003 Gamma-ray transition cross section for the 780.2 keV 2299001300004 transition L11 -> L1 of Th-232. 2299001300005 EN-SEC (E,G) Energy of gamma transition. 2299001300006 ADD-RES (COMP) Compared with TALYS code calculation. 2299001300007 STATUS (PRELM) Preliminary data. 2299001300008 Data are on Fig.7 middle bottom of C,2011KRAKOW . 2299001300009 ENDBIB 7 0 2299001300010 COMMON 1 3 2299001300011 E 2299001300012 KEV 2299001300013 780.2 2299001300014 ENDCOMMON 3 0 2299001300015 NODATA 0 0 2299001300016 ENDSUBENT 15 0 2299001399999 SUBENT 22990014 20130920 22352299001400001 BIB 4 7 2299001400002 REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299001400003 Gamma-ray transition cross section for the 681.1 keV 2299001400004 transition L6 -> L1 of Th-232. 2299001400005 EN-SEC (E,G) Energy of gamma transition. 2299001400006 ADD-RES (COMP) Compared with TALYS code calculation. 2299001400007 STATUS (PRELM) Preliminary data. 2299001400008 Data are on Fig.7 right bottom of C,2011KRAKOW . 2299001400009 ENDBIB 7 0 2299001400010 COMMON 1 3 2299001400011 E 2299001400012 KEV 2299001400013 681.1 2299001400014 ENDCOMMON 3 0 2299001400015 NODATA 0 0 2299001400016 ENDSUBENT 15 0 2299001499999 SUBENT 22990015 20130920 22352299001500001 BIB 4 7 2299001500002 REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299001500003 Gamma-ray transition cross section for the 774.1 keV 2299001500004 transition L7 -> L0 of Th-232. 2299001500005 EN-SEC (E,G) Energy of gamma transition. 2299001500006 ADD-RES (COMP) Compared with TALYS code calculation. 2299001500007 STATUS (PRELM) Preliminary data. 2299001500008 Data are on Fig.7 right bottom of C,2011KRAKOW . 2299001500009 ENDBIB 7 0 2299001500010 COMMON 2 3 2299001500011 E LVL-FIN 2299001500012 KEV NO-DIM 2299001500013 774.1 0. 2299001500014 ENDCOMMON 3 0 2299001500015 NODATA 0 0 2299001500016 ENDSUBENT 15 0 2299001599999 ENDENTRY 15 0 2299099999999