ENTRY 22941 20200909 22912294100000001 SUBENT 22941001 20200909 22912294100100001 BIB 15 136 2294100100002 TITLE Cross section measurements for thermal neutron-induced 2294100100003 reactions on actinides at the ILL reactor 2294100100004 AUTHOR (A.Letourneau, E.Dupont, P.Mutti, S.Panebianco, 2294100100005 O.Bringer, I.Al Mahamid, Ch.Blandin, 2294100100006 S.Chabod, F.Chartier, G.Fioni, H.Isnard, 2294100100007 F.Marie, L.Oriol, Ch.Veyssiere) 2294100100008 INSTITUTE (2FR SAC) Bringer, Chabod, Dupont, Fioni, Marie, 2294100100009 Letourneau, Panebianco, Veyssiere - CEA/Saclay 2294100100010 (2FR CAD) Blandin, Oriol - CEA/Cadarache, Saint-Paul- 2294100100011 lez-Durances, France 2294100100012 Chartier, Isnard - CEA/Cadarache, Gif-sur- 2294100100013 Yvette, France. 2294100100014 (2FR ILL) Mutti, Institute Laue-Langevin, Grenoble 2294100100015 (1USABRK) Al Mahamid, Lawrence Berkeley Nat.Lab. 2294100100016 REFERENCE (C,2009BUDA,,81,2009) Th-232,Pa-233,U-234,-235,Np-237,2294100100017 Pu-238,Am-241,242m,Cm-242, Cm-244,Cf-249 capture c-s; 2294100100018 Np-238,Am-242g,-242m,Cm-245 fission c-s in Tables. 2294100100019 Proc. of the Scientific Workshop on Nuclear Data 2294100100020 Measurements, Theory and Applications. Budapest, 2294100100021 Hungary, 23-25 September 2009, edited by Tamas Belgya.2294100100022 (C,2007NICE,1,619,200704) First author O.Bringer 2294100100023 #doi:10.1051/ndata:07612 2294100100024 (C,2007CORSEN,,63,200710) Data for Np, Am and Cm-245. 2294100100025 (J,NIM/A,591,(3),510,200807) Data for Th,Pa,U. 2294100100026 #doi:10.1016/j.nima.2008.01.067 2294100100027 First author O.Bringer 2294100100028 (C,2006VANCOU,,(C034),2006) PHYSOR-2006, ANS Topical 2294100100029 Meeting in Reactor Physics, Vancouver, Canada, 2294100100030 10-14 Sept 2006, Rept # C034. First publication. 2294100100031 First author O.Bringer. 2294100100032 (R,INDC(NDS)-0574,85,2010) Np-237, Th-232,Pa-233,U-234,2294100100033 U-235,Pu-238, Np-238, Cm-244, Cm-245 2294100100034 REL-REF (M,22924001,F.Marie+,J,NIM/A,556,547,2006) The other 2294100100035 conditions of experiment. 2294100100036 (M,22696001,G.Fioni+,J,NP/A,693,546,2001) The details 2294100100037 experiments. 2294100100038 (M,,S.Chabod+,J,NIM/A,566,633,2006) Details of fission 2294100100039 chambers functioning. 2294100100040 MERCS code from : 2294100100041 http//www-dapnia.cea.fr/Sphn/MNM/Modelisation. 2294100100042 (I,,M.Fadil,T,FADIL,2003) Ph.D. thesis, INP Grenoble, 2294100100043 2003 (in French). Details of neutron flux. 2294100100044 FACILITY (REAC,2FR ILL) High flux reactor of Laue-Langevin 2294100100045 Institute in Grenoble, MINI-INCA (incineration of 2294100100046 actinides) set-up. 2294100100047 INC-SPECT Three irradiation channels could be used. 2294100100048 -The T4 channel provide pure thermal neutrons with 2294100100049 an intensity of the order of 2. x 10**13 n/cm2/s. 2294100100050 -The V4 channel can provide different irradiation 2294100100051 positions with different neutron flux/energy spectra- 2294100100052 the thermal neutron proportion varies from 100% to 85%2294100100053 and intensities range from 6. x 10**13 n/cm2/s to 2294100100054 1.5 x 10**15 n/cm2/s. 2294100100055 -The H9 channel has a neutron flux close to the one 2294100100056 available in an intermediate position of the V4 one. 2294100100057 MCNP code was used to calculate neutron flux 2294100100058 distributions at different irradiation positions - 2294100100059 see Fig.2 of C,2007NICE. 2294100100060 Mean neutron flux F measured: 2294100100061 Position F,n/s/cm2 Fthermal/F 2294100100062 25 cm 8. x 10**14 0.898 2294100100063 50 cm 7.96 x 10**14 0.966 2294100100064 75 cm 4.3 x 10**14 0.997 2294100100065 100 cm 5.5 x 10**13 1.000 2294100100066 H9 6. x 10**14 0.981 2294100100067 ,where F - mean neutron flux measured in 2294100100068 M.Fadil, Ph.D. thesis, INP Grenoble, 2003 (in French).2294100100069 Fth - thermal component defined with cut 1 eV. 2294100100070 INC-SOURCE (REAC) 2294100100071 METHOD (GSPEC) Gamma- and alpha-spectroscopy bench allows 2294100100072 (ASPEC) fast characterization of irradiated samples and2294100100073 direct access to short-lived isotopes. 2294100100074 (MASSP) Precise mass spectrometry (Thermal Ionization 2294100100075 and Inductive Coupled Plasma Mass Spectrometry) 2294100100076 analysis can be performed after irradiation in V4. 2294100100077 ANALYSIS Reaction chain analysis with the help of ROOT MERCS 2294100100078 analysis code. MERCS was used for fit of nuclear 2294100100079 parameters on exp. data and to optimize irradiation 2294100100080 conditions -suitable neutron flux and irradiation time.2294100100081 In mass spectrometry analysis the free parameters were:2294100100082 Am-241, Am-242m, Cm-242m capture c-s and Am-241 2294100100083 isomeric branching ration. 2294100100084 In fission chamber analysis the previously measured 2294100100085 Am-241 capture and branching ratio were used as input 2294100100086 parameters - to obtain Am-242 fission c-s. 2294100100087 PART-DET (A,G,FF) 2294100100088 DETECTOR (SPEC,SI,HPGE) Lohengrin mass spectrometer, equipped 2294100100089 with Si- and Ge-detectors (at H9 channel). 2294100100090 The Si and Ge-detector electronic system is able to 2294100100091 record in high counting rates up to 80-kHz for Ge- 2294100100092 detector and up to 20-kHz for Si-detector. 2294100100093 (FISCH) At V4 channel. Microscopic fission chambers - 2294100100094 Triple-Deposit Fission-Chambers (TDFC). Operates 2294100100095 in current mode to measure on-line the actinide fission2294100100096 current with respect to known U-235 fission current. 2294100100097 Each fis. chamber 2 cm long,8 mm in diameter, filled 2294100100098 with pure argon gas. 2294100100099 MONITOR (27-CO-59(N,G)27-CO-60,,SIG,,SPA) 2294100100100 (92-U-235(N,F),,SIG,,SPA) 2294100100101 Effective cross section of standard reactions were 2294100100102 used to normalize the neutron flux: 2294100100103 Position Co-59(n,gamma) U-235(n,f) Fth/F 2294100100104 25 cm 28.33 424.68 0.898 2294100100105 50 cm 30.74 466.83 0.966 2294100100106 75 cm 31.66 484.17 0.997 2294100100107 100 cm 31.84 487.29 1.000 2294100100108 H9 31.10 473.93 0.981 2294100100109 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained. 2294100100110 HISTORY (20070119C) S.M. 2294100100111 (20070524A) Corrections have been done IN SAN 002 2294100100112 according to N.Otsuka remark 2294100100113 (20080514A) Average energy changed. REACTION keyword 2294100100114 in SAN 007 corrected 2294100100115 (20090320A) M.M. Misprints were corrected. 2294100100116 Two references C,2007NICE and NIM/A,591 were added. 2294100100117 Subents 002 - 011 were corrected. 2294100100118 Subents 012 - 040 were added. 2294100100119 (20090911A) M.M. Reference C,2007CORSEN was added. 2294100100120 BIB information was added. 2294100100121 Subents 012-014, 019-22, 031-034, 037,039,040 were 2294100100122 corrected according to C,2007CORSEN data. 2294100100123 Subent 041 was added. 2294100100124 (20100327A) MM. Subents 031, 032 were corrected. 2294100100125 (20120108A) MM. Reference C,2009BUDA was added. 2294100100126 BIB information was added. Data was corrected 2294100100127 according to C,2009BUDA. Subents 042,43 were added. 2294100100128 Subents 013-041 were corrected. 2294100100129 (20131221A) SD: REACTION code in Subent 7 was corrected2294100100130 (20151216A) SD: REACTION code corrected in Subents 039,2294100100131 0040, 042, 043. Title update following first ref. 2294100100132 Cosmetic corrections in other Subents. 2294100100133 (20160910A) M.M. Ref. R,INDC(NDS)-0574,85,2010 was 2294100100134 added. STATUS was updated in Subents 2294100100135 Subents 044, 045 were added. 2294100100136 EN -> EN-MEAN for spectrum average data. 2294100100137 (20200909U) SD: BIB updated in Subent 044. 2294100100138 ENDBIB 136 0 2294100100139 NOCOMMON 0 0 2294100100140 ENDSUBENT 139 0 2294100199999 SUBENT 22941002 20160910 22542294100200001 BIB 7 21 2294100200002 REACTION (95-AM-241(N,G)95-AM-242-G/T,,SIG/RAT,,SPA) Value 2294100200003 i.b.r. in authors notation. No additional information 2294100200004 is given 2294100200005 METHOD (MASSP) Mass-spectrometry of irradiated samples 2294100200006 INC-SPECT .Thermal Maxwellian with epithermal neutron admixture 2294100200007 SAMPLE .The samples were 97% in purity of Am-241 with 2.5% 2294100200008 of Np-237 and with some plutonium traces. Two sets 2294100200009 were irradiated for 11 and 24-days in the T4 channel, 2294100200010 whereas four other sets were irradiated in the 2294100200011 H9-channel for 1, 5, 11 and 19-days.Cooling time 1 yr.2294100200012 ANALYSIS .The obtained values result from the average over T4 2294100200013 and H9 channel measurements after correction from 2294100200014 experimental values. 2294100200015 STATUS (TABLE) Table 1 in reference C,2006VANCOU. 2294100200016 (COREL,22696003) Complement measurement of the data set2294100200017 compiled in Subent 22696003. 2294100200018 (SPSDD,22941012) Superseded by newer published value. 2294100200019 HISTORY (20070524A) S.M. - Corrections have been done in 2294100200020 REACTION SF4 of SAN 002: G/M to G/T. 2294100200021 (20090320A) SPSDD was added in STATUS. 2294100200022 (20160910A) EN -> EN-MEAN. 2294100200023 ENDBIB 21 0 2294100200024 NOCOMMON 0 0 2294100200025 DATA 3 1 2294100200026 EN-MEAN DATA DATA-ERR 2294100200027 MILLI-EV NO-DIM NO-DIM 2294100200028 25. 0.895030 0.001632 2294100200029 ENDDATA 3 0 2294100200030 ENDSUBENT 29 0 2294100299999 SUBENT 22941003 20160910 22542294100300001 BIB 5 10 2294100300002 REACTION (95-AM-241(N,G)95-AM-242,,SIG,,SPA) 2294100300003 METHOD (MASSP) Mass-spectrometry of irradiated samples 2294100300004 INC-SPECT .Thermal Maxwellian with epithermal admixture 2294100300005 STATUS (PRELM) As specified by authors 2294100300006 (SPSDD,22941013) Superseded by newer published value. 2294100300007 (TABLE) Table 1 in 2006VANCOU,,(C034),2006 2294100300008 (DEP,22941002) 2294100300009 HISTORY (20090320A) SPSDD was added in STATUS. 2294100300010 (20151216U) SD: text in STATUS modified. 2294100300011 (20160910A) EN -> EN-MEAN. 2294100300012 ENDBIB 10 0 2294100300013 NOCOMMON 0 0 2294100300014 DATA 3 1 2294100300015 EN-MEAN DATA DATA-ERR 2294100300016 MILLI-EV B B 2294100300017 25. 714.179 23.34 2294100300018 ENDDATA 3 0 2294100300019 ENDSUBENT 18 0 2294100399999 SUBENT 22941004 20160910 22542294100400001 BIB 5 9 2294100400002 REACTION (95-AM-242-M(N,G)95-AM-243,,SIG,,SPA) 2294100400003 METHOD (MASSP) Mass-spectrometry of irradiated samples 2294100400004 INC-SPECT .Thermal Maxwellian with epithermal admixture 2294100400005 STATUS (TABLE) Table 1 in 2006VANCOU,,(C034),2006. 2294100400006 (DEP,22941002) 2294100400007 (SPSDD,22941015) Superseded by newer published value. 2294100400008 HISTORY (20090320A) SPSDD was added in STATUS. 2294100400009 (20151216U) SD: text in STATUS modified. 2294100400010 (20160910A) EN -> EN-MEAN. 2294100400011 ENDBIB 9 0 2294100400012 NOCOMMON 0 0 2294100400013 DATA 3 1 2294100400014 EN-MEAN DATA DATA-ERR 2294100400015 MILLI-EV B B 2294100400016 25. 1147.49 114.103 2294100400017 ENDDATA 3 0 2294100400018 ENDSUBENT 17 0 2294100499999 SUBENT 22941005 20160910 22542294100500001 BIB 5 9 2294100500002 REACTION (96-CM-242(N,G)96-CM-243,,SIG,,SPA) 2294100500003 METHOD (MASSP) Mass-spectrometry of irradiated samples 2294100500004 INC-SPECT .Thermal Maxwellian with epithermal admixture 2294100500005 STATUS (TABLE) Table 1 in 2006VANCOU,,(C034),2006. 2294100500006 (DEP,22941002) 2294100500007 (SPSDD,22941017) Superseded by newer published value. 2294100500008 HISTORY (20090320A) SPSDD was added in STATUS. 2294100500009 (20151216U) SD: text in STATUS modified. 2294100500010 (20160910A) EN -> EN-MEAN. 2294100500011 ENDBIB 9 0 2294100500012 NOCOMMON 0 0 2294100500013 DATA 3 1 2294100500014 EN-MEAN DATA DATA-ERR 2294100500015 MILLI-EV B PER-CENT 2294100500016 25. 20.968 1.82 2294100500017 ENDDATA 3 0 2294100500018 ENDSUBENT 17 0 2294100599999 SUBENT 22941006 20160910 22542294100600001 BIB 7 21 2294100600002 REACTION (95-AM-242-M(N,F),,SIG,,MXW) 2294100600003 METHOD (MASSP) Mass-spectrometry of irradiated samples 2294100600004 DETECTOR (IOCH) Specific fission micro-chambers were developed 2294100600005 to sustain high neutron fluxes and high temperature 2294100600006 conditions-small gap ionization chambers filled with 2294100600007 pure argon gas. For MA-transmutation studies, triple- 2294100600008 barrel fission chambers-three electrically independent2294100600009 fission chambers which are sharing the same gas. 2294100600010 INC-SPECT .Pure thermal Maxwellian 2294100600011 COMMENT *By authors*.In order to determine with a better 2294100600012 precision the both Am-242 fission cross sections, 2294100600013 three fission chambers with Am-241, U-235 and 2294100600014 non-deposits for 44-days at the upper position of the 2294100600015 V4 channel were irradiated. 2294100600016 STATUS (PRELM) 2294100600017 (TABLE) Table 1 in 2006VANCOU,,(C034),2006. 2294100600018 (DEP,22941002) 2294100600019 (SPSDD,22941019) Superseded by newer published value. 2294100600020 HISTORY (20090320A) SPSDD was added in STATUS. 2294100600021 (20151216U) SD: text in STATUS modified. 2294100600022 (20160910A) EN -> EN-MEAN. 2294100600023 ENDBIB 21 0 2294100600024 NOCOMMON 0 0 2294100600025 DATA 3 1 2294100600026 EN-MEAN DATA DATA-ERR 2294100600027 MILLI-EV B B 2294100600028 25. 6838.71 341.94 2294100600029 ENDDATA 3 0 2294100600030 ENDSUBENT 29 0 2294100699999 SUBENT 22941007 20160910 22542294100700001 BIB 7 27 2294100700002 REACTION (95-AM-242(N,F),,SIG,,MXW) 2294100700003 METHOD (MASSP) Mass-spectrometry of irradiated samples 2294100700004 DETECTOR (IOCH) Specific fission micro-chambers were developed 2294100700005 to sustain high neutron fluxes and high temperature 2294100700006 conditions-small gap ionization chambers filled with 2294100700007 pure argon gas. For MA-transmutation studies, triple- 2294100700008 barrel fission chambers-three electrically independent2294100700009 fission chambers which are sharing the same gas. 2294100700010 INC-SPECT .Pure thermal Maxwellian 2294100700011 COMMENT *By authors*.In order to determine with a better 2294100700012 precision the both Am-242 fission cross sections, 2294100700013 three fission chambers with Am-241, U-235 and 2294100700014 non-deposits for 44-days at the upper position of the 2294100700015 V4 channel were irradiated. 2294100700016 STATUS (PRELM) 2294100700017 (TABLE) Table 1 in 2006VANCOU,,(C034),2006. 2294100700018 (DEP,22941002) 2294100700019 (SPSDD,22941021) Superseded by newer published value. 2294100700020 HISTORY (20080514A) REACTION SF1 changed from Am-242-G 2294100700021 to Am-242 2294100700022 (20090320A) M.M. Misprints were corrected. 2294100700023 BIB information was added. SPSDD was added in STATUS. 2294100700024 Am-242 -> Am-242-G according to Table 1, C,2006VANCOU.2294100700025 (20131221A) SD: AM-242-G -> AM-242 in REACTION 2294100700026 according to N.Otsuka comment (NDS,IAEA). 2294100700027 (20151216U) SD: text in STATUS modified. 2294100700028 (20160910A) EN -> EN-MEAN. 2294100700029 ENDBIB 27 0 2294100700030 NOCOMMON 0 0 2294100700031 DATA 3 1 2294100700032 EN-MEAN DATA DATA-ERR 2294100700033 MILLI-EV B B 2294100700034 25. 2892.69 173.56 2294100700035 ENDDATA 3 0 2294100700036 ENDSUBENT 35 0 2294100799999 SUBENT 22941008 20160910 22542294100800001 BIB 7 9 2294100800002 REACTION (90-TH-232(N,G)90-TH-233,,SIG,,SPA) 2294100800003 METHOD .Fission chamber analysis 2294100800004 INC-SPECT .Thermal Maxwellian with epithermal admixture 2294100800005 SAMPLE A pure 100-microg Th-232 sample in the V4 channel. 2294100800006 MONITOR (27-CO-59(N,G)27-CO-60,,SIG,,SPA) For neutron fluency. 2294100800007 STATUS (TABLE) Table 2 in C,2006VANCOU. 2294100800008 (SPSDD,22941023) Superseded by newer published value 2294100800009 HISTORY (20090320A) SPSDD was added in STATUS. 2294100800010 (20160910A) EN -> EN-MEAN. 2294100800011 ENDBIB 9 0 2294100800012 NOCOMMON 0 0 2294100800013 DATA 3 1 2294100800014 EN-MEAN DATA DATA-ERR 2294100800015 MILLI-EV B B 2294100800016 25. 7.40 0.21 2294100800017 ENDDATA 3 0 2294100800018 ENDSUBENT 17 0 2294100899999 SUBENT 22941009 20160910 22542294100900001 BIB 5 9 2294100900002 REACTION (91-PA-233(N,G)91-PA-234,,SIG,,SPA) 2294100900003 METHOD .Fission chamber analysis 2294100900004 INC-SPECT .Thermal Maxwellian with epithermal admixture 2294100900005 STATUS (TABLE) Table 2 in 2006VANCOU,,(C034),2006. 2294100900006 (DEP,22941008) 2294100900007 (SPSDD,22941025) Superseded by newer published value 2294100900008 HISTORY (20090320A) SPSDD was added in STATUS. 2294100900009 (20151216U) SD: text in STATUS modified. 2294100900010 (20160910A) EN -> EN-MEAN. 2294100900011 ENDBIB 9 0 2294100900012 NOCOMMON 0 0 2294100900013 DATA 3 1 2294100900014 EN-MEAN DATA DATA-ERR 2294100900015 MILLI-EV B B 2294100900016 25. 39.41 0.14 2294100900017 ENDDATA 3 0 2294100900018 ENDSUBENT 17 0 2294100999999 SUBENT 22941010 20160910 22542294101000001 BIB 5 10 2294101000002 REACTION (92-U-234(N,G)92-U-235,,SIG,,SPA) 2294101000003 METHOD .Fission chamber analysis 2294101000004 INC-SPECT .Thermal Maxwellian with epithermal admixture 2294101000005 STATUS (TABLE) Table 2 of 2006VANCOU. 2294101000006 (DEP,22941008) 2294101000007 (SPSDD,22941027) Superseded by newer published value 2294101000008 HISTORY (20090320A) SPSDD was added in STATUS. 2294101000009 REACTION was changed (N,F) -> (N,G) according to 2294101000010 titles of Table 2. 2294101000011 (20160910A) EN -> EN-MEAN. 2294101000012 ENDBIB 10 0 2294101000013 NOCOMMON 0 0 2294101000014 DATA 3 1 2294101000015 EN-MEAN DATA DATA-ERR 2294101000016 MILLI-EV B B 2294101000017 25. 98.37 3.1 2294101000018 ENDDATA 3 0 2294101000019 ENDSUBENT 18 0 2294101099999 SUBENT 22941011 20160910 22542294101100001 BIB 5 10 2294101100002 REACTION (92-U-235(N,G)92-U-236,,SIG,,SPA) 2294101100003 METHOD .Fission chamber analysis 2294101100004 INC-SPECT .Thermal Maxwellian with epithermal admixture 2294101100005 STATUS (TABLE) Table 2 in 2006VANCOU,,(C034),2006. 2294101100006 (DEP,22941008) 2294101100007 (SPSDD,22941029) Superseded by newer published value 2294101100008 HISTORY (20090320A) SPSDD was added in STATUS. REACTION was 2294101100009 changed (n,f) -> (n,g) according to titles of Table 2. 2294101100010 (20151216U) SD: text in STATUS modified. 2294101100011 (20160910A) EN -> EN-MEAN. 2294101100012 ENDBIB 10 0 2294101100013 NOCOMMON 0 0 2294101100014 DATA 3 1 2294101100015 EN-MEAN DATA DATA-ERR 2294101100016 MILLI-EV B B 2294101100017 25. 96.65 11.07 2294101100018 ENDDATA 3 0 2294101100019 ENDSUBENT 18 0 2294101199999 SUBENT 22941012 20160910 22542294101200001 BIB 5 10 2294101200002 REACTION (95-AM-241(N,G)95-AM-242-G/T,,SIG/RAT,,MXW) 2294101200003 Isomeric branching ratio. 2294101200004 METHOD (MASSP) Post irradiation mass-spectrometry analysis. 2294101200005 INC-SPECT Pure Maxwellian neutron flux. 2294101200006 STATUS (TABLE) Table 3 of C,2007CORSEN . 2294101200007 HISTORY (20090320C) M.M. Subent added . 2294101200008 (20090911A) M.M. Data error was changed into newer 2294101200009 value from 2007CORSEN. 2294101200010 DERIV was deleted in REACTION. 2294101200011 (20160910A) EN -> EN-MEAN. 2294101200012 ENDBIB 10 0 2294101200013 NOCOMMON 0 0 2294101200014 DATA 3 1 2294101200015 EN-MEAN DATA DATA-ERR 2294101200016 EV NO-DIM NO-DIM 2294101200017 0.0253 0.8947 0.004 2294101200018 ENDDATA 3 0 2294101200019 ENDSUBENT 18 0 2294101299999 SUBENT 22941013 20120108 22302294101300001 BIB 6 14 2294101300002 REACTION (95-AM-241(N,G)95-AM-242,,SIG,,MXW/FCT) 2294101300003 Maxwellian averaged cross-section multiplied by 2294101300004 sqrt(pi)/2 (as compared to the Westcott convention) 2294101300005 ANALYSIS Effective cross sections were extracted by evaluated 2294101300006 data of libraries and calculated neutron flux. 2294101300007 METHOD (MASSP) Post irradiation mass-spectrometry analysis. 2294101300008 INC-SPECT Pure Maxwellian neutron flux. 2294101300009 STATUS (TABLE) Table 4 of C,2009BUDA. 2294101300010 Table 3 of C,2007CORSEN (609.+-27. b ). 2294101300011 Table 4 of C,2007NICE (609.+-20 b) 2294101300012 HISTORY (20090320C) Subent was added . 2294101300013 (20090911A) M.M. Data error was changed into newer 2294101300014 value from 2007CORSEN. 2294101300015 (20120108A) Data were corrected as given in C,2009BUDA.2294101300016 ENDBIB 14 0 2294101300017 NOCOMMON 0 0 2294101300018 DATA 3 1 2294101300019 EN-MEAN DATA DATA-ERR 2294101300020 EV B B 2294101300021 0.0253 609. 20. 2294101300022 ENDDATA 3 0 2294101300023 ENDSUBENT 22 0 2294101399999 SUBENT 22941014 20120108 22302294101400001 BIB 4 12 2294101400002 REACTION (95-AM-241(N,G)95-AM-242,,SIG) 2294101400003 ANALYSIS 25.3 meV value was extracted from measured effective 2294101400004 cross section using the ratio of 25.3 meV c-s to 2294101400005 effective cross, calculated from data bases. 2294101400006 STATUS (TABLE) Table 4 of C,2009BUDA,81,2009. 2294101400007 Table 3 of C,2007CORSEN (704+-32.) 2294101400008 Table 4 of C,2007NICE (705.+-23 b). 2294101400009 (DEP,22941013) 2294101400010 HISTORY (20090320C) Subent was added. 2294101400011 (20090911A) M.M. Data and error were changed into newer2294101400012 values from C,2007CORSEN. 2294101400013 (20120108A) Data were corrected as given in C,2009BUDA.2294101400014 ENDBIB 12 0 2294101400015 NOCOMMON 0 0 2294101400016 DATA 3 1 2294101400017 EN DATA DATA-ERR 2294101400018 EV B B 2294101400019 0.0253 700. 23. 2294101400020 ENDDATA 3 0 2294101400021 ENDSUBENT 20 0 2294101499999 SUBENT 22941015 20120108 22302294101500001 BIB 6 11 2294101500002 REACTION (95-AM-242-M(N,G)95-AM-243,,SIG,,MXW/FCT) 2294101500003 Maxwellian averaged cross-section multiplied by 2294101500004 sqrt(pi)/2 (as compared to the Westcott convention) 2294101500005 ANALYSIS Effective cross sections were extracted by evaluated 2294101500006 data of libraries and calculated neutron flux. 2294101500007 METHOD (MASSP) Post irradiation mass-spectrometry analysis. 2294101500008 INC-SPECT Pure Maxwellian neutron flux. 2294101500009 STATUS (TABLE) Table 4 of C,2009BUDA,81,2009. 2294101500010 Table 4 of C,2007NICE (1131.+-108.) . 2294101500011 HISTORY (20090320C) Subent was added. 2294101500012 (20120108A) Data were corrected as given in C,2009BUDA.2294101500013 ENDBIB 11 0 2294101500014 NOCOMMON 0 0 2294101500015 DATA 3 1 2294101500016 EN-MEAN DATA DATA-ERR 2294101500017 EV B B 2294101500018 0.0253 1074. 108. 2294101500019 ENDDATA 3 0 2294101500020 ENDSUBENT 19 0 2294101599999 SUBENT 22941016 20120108 22302294101600001 BIB 4 10 2294101600002 REACTION (95-AM-242-M(N,G)95-AM-243,,SIG) 2294101600003 ANALYSIS 25.3 meV value was extracted from measured effective 2294101600004 cross section using the ratio of 25.3 meV c-s to 2294101600005 effective cross, calculated from data bases. 2294101600006 STATUS (TABLE) Table 4 of C,2009BUDA,81,2009. 2294101600007 Table 4 of C,2007NICE (1161+-111). 2294101600008 (PRELM) Preliminary results. 2294101600009 (DEP,22941015) 2294101600010 HISTORY (20090320C) Subent was added. 2294101600011 (20120108A) Data were corrected as given in C,2009BUDA.2294101600012 ENDBIB 10 0 2294101600013 NOCOMMON 0 0 2294101600014 DATA 3 1 2294101600015 EN DATA DATA-ERR 2294101600016 EV B B 2294101600017 0.0253 1152. 112. 2294101600018 ENDDATA 3 0 2294101600019 ENDSUBENT 18 0 2294101699999 SUBENT 22941017 20120108 22302294101700001 BIB 6 12 2294101700002 REACTION (96-CM-242(N,G)96-CM-243,,SIG,,MXW/FCT) 2294101700003 Maxwellian averaged cross-section multiplied by 2294101700004 sqrt(pi)/2 (as compared to the Westcott convention) 2294101700005 ANALYSIS Effective cross sections were extracted by evaluated 2294101700006 data of libraries and calculated neutron flux. 2294101700007 METHOD (MASSP) Post irradiation mass-spectrometry analysis. 2294101700008 INC-SPECT Pure Maxwellian neutron flux. 2294101700009 STATUS (TABLE) Table 4 of C,2009BUDA,81,2009. 2294101700010 Table 4 of C,2007NICE (19.4+-1.5). 2294101700011 (PRELM) Preliminary results. 2294101700012 HISTORY (20090320C) Subent was added. 2294101700013 (20120108A) Data were corrected as given in C,2009BUDA.2294101700014 ENDBIB 12 0 2294101700015 NOCOMMON 0 0 2294101700016 DATA 3 1 2294101700017 EN-MEAN DATA DATA-ERR 2294101700018 EV B B 2294101700019 0.0253 15.82 1.2 2294101700020 ENDDATA 3 0 2294101700021 ENDSUBENT 20 0 2294101799999 SUBENT 22941018 20120108 22302294101800001 BIB 4 9 2294101800002 REACTION (96-CM-242(N,G)96-CM-243,,SIG) 2294101800003 ANALYSIS 25.3 meV value was extracted from measured effective 2294101800004 cross section using the ratio of 25.3 meV c-s to 2294101800005 effective cross, calculated from data bases. 2294101800006 STATUS (TABLE) Table 4 of C,2009BUDA,81,2009. 2294101800007 Table 4 of C,2007NICE (19.1+-1.5 b) . 2294101800008 (PRELM) Preliminary results. 2294101800009 (DEP,22941017) 2294101800010 HISTORY (20090320C) Subent was added. 2294101800011 ENDBIB 9 0 2294101800012 NOCOMMON 0 0 2294101800013 DATA 3 1 2294101800014 EN DATA DATA-ERR 2294101800015 EV B B 2294101800016 0.0253 19.1 1.5 2294101800017 ENDDATA 3 0 2294101800018 ENDSUBENT 17 0 2294101899999 SUBENT 22941019 20120108 22302294101900001 BIB 6 15 2294101900002 REACTION (95-AM-242-M(N,F),,SIG,,MXW/FCT) 2294101900003 Maxwellian averaged cross-section multiplied by 2294101900004 sqrt(pi)/2 (as compared to the Westcott convention) 2294101900005 ANALYSIS Effective cross sections were extracted by evaluated 2294101900006 data of libraries and calculated neutron flux. 2294101900007 METHOD Fission chambers measurement. 2294101900008 INC-SPECT Pure Maxwellian neutron flux. 2294101900009 STATUS (TABLE) Table 4 of C,2009BUDA,81,2009. 2294101900010 Table 3 of C,2007CORSEN (6527.+-225. b). 2294101900011 Table 4 of C,2007NICE (6526.+-625.b) . 2294101900012 (PRELM) Preliminary results. 2294101900013 HISTORY (20090320A) Subent was added. 2294101900014 (20090911A) M.M. Data and error were changed into newer2294101900015 values from C,2007CORSEN. 2294101900016 (20120108A) Data were corrected as given in C,2009BUDA.2294101900017 ENDBIB 15 0 2294101900018 NOCOMMON 0 0 2294101900019 DATA 3 1 2294101900020 EN-MEAN DATA DATA-ERR 2294101900021 EV B B 2294101900022 0.0253 6527. 625. 2294101900023 ENDDATA 3 0 2294101900024 ENDSUBENT 23 0 2294101999999 SUBENT 22941020 20120108 22302294102000001 BIB 4 12 2294102000002 REACTION (95-AM-242-M(N,F),,SIG) 2294102000003 ANALYSIS 25.3 meV value was extracted from measured effective 2294102000004 cross section using the ratio of 25.3 meV c-s to 2294102000005 effective cross, calculated from data bases. 2294102000006 STATUS (TABLE) Table 4 of C,2009BUDA,81,2009. 2294102000007 Table 3 of C,2007CORSEN (6856.+-656. b). 2294102000008 Table 4 of C,2007NICE (6855.97+-657. b) . 2294102000009 (PRELM) Preliminary results. 2294102000010 (DEP,22941019) 2294102000011 HISTORY (20090320A) Subent was added. 2294102000012 (20090911A) M.M. Data and error were changed into newer2294102000013 values from C,2007CORSEN. 2294102000014 ENDBIB 12 0 2294102000015 NOCOMMON 0 0 2294102000016 DATA 3 1 2294102000017 EN DATA DATA-ERR 2294102000018 EV B B 2294102000019 0.0253 6856. 656. 2294102000020 ENDDATA 3 0 2294102000021 ENDSUBENT 20 0 2294102099999 SUBENT 22941021 20120108 22302294102100001 BIB 6 16 2294102100002 REACTION (95-AM-242(N,F),,SIG,,MXW/FCT) 2294102100003 Maxwellian averaged cross-section multiplied by 2294102100004 sqrt(pi)/2 (as compared to the Westcott convention) 2294102100005 ANALYSIS Effective cross sections were extracted by evaluated 2294102100006 data of libraries and calculated neutron flux. 2294102100007 METHOD Fission chambers measurement. 2294102100008 INC-SPECT Pure Maxwellian neutron flux. 2294102100009 STATUS (TABLE) Table 4 of C,2009BUDA,81,2009. 2294102100010 Table 3 of C,2007CORSEN (2224.+-215. b). 2294102100011 Table 4 of C,2007NICE (2225.+-215. b) . 2294102100012 (PRELM) Preliminary results. 2294102100013 HISTORY (20090320A) Subent was added. 2294102100014 (20090911A) M.M. Data value was changed into newer 2294102100015 value from C,2007CORSEN. 2294102100016 (20120621A) AM-242-G -> AM-242 in REACTION according to2294102100017 N.Otsuka comment (NDS,IAEA). 2294102100018 ENDBIB 16 0 2294102100019 NOCOMMON 0 0 2294102100020 DATA 3 1 2294102100021 EN-MEAN DATA DATA-ERR 2294102100022 EV B B 2294102100023 0.0253 2224. 215. 2294102100024 ENDDATA 3 0 2294102100025 ENDSUBENT 24 0 2294102199999 SUBENT 22941022 20120108 22302294102200001 BIB 4 15 2294102200002 REACTION (95-AM-242(N,F),,SIG) 2294102200003 ANALYSIS 25.3 meV value was extracted from measured effective 2294102200004 cross section using the ratio of 25.3 meV c-s to 2294102200005 effective cross, calculated from data bases. 2294102200006 STATUS (TABLE) Table 4 of C,2009BUDA,81,2009. 2294102200007 Table 3 of C,2007CORSEN (2644.+-281. b) . 2294102200008 Table 4 of C,2007NICE (2644.07+-257. b) . 2294102200009 (PRELM) Preliminary results. 2294102200010 (DEP,22941021) 2294102200011 HISTORY (20090320A) Subent was added. 2294102200012 (20090911A) M.M. Data and error were changed into newer2294102200013 values from C,2007CORSEN. 2294102200014 (20120108A) Data were corrected as given in C,2009BUDA.2294102200015 AM-242-G -> AM-242 in REACTION according to2294102200016 N.Otsuka comment (NDS,IAEA). 2294102200017 ENDBIB 15 0 2294102200018 NOCOMMON 0 0 2294102200019 DATA 3 1 2294102200020 EN DATA DATA-ERR 2294102200021 EV B B 2294102200022 0.0253 2472. 281. 2294102200023 ENDDATA 3 0 2294102200024 ENDSUBENT 23 0 2294102299999 SUBENT 22941023 20160910 22542294102300001 BIB 9 32 2294102300002 REACTION (90-TH-232(N,G)90-TH-233,,SIG,,SPA) 2294102300003 SAMPLE Pure 100-microgram Th-232 sample in nitrate powder form2294102300004 canned in quartz capsule placed in Al container. 2294102300005 INC-SPECT Thermal Maxwellian flux.Neutron fluency was measured by2294102300006 Al-0.1%Co-59 monitor. Less 3% of neutrons have energy 2294102300007 greater 1 eV. Neutron flux in analysis was assumed to 2294102300008 be constant at (7.56+-0.23)[10**14 n/cm**2/s(measured).2294102300009 METHOD (MASSP) Precise mass spectrometry (Thermal Ionization 2294102300010 and Inductive Coupled Plasma Mass Spectrometry) 2294102300011 analysis after 43 day irradiation in V4 at 50 cm 2294102300012 distance from fuel element. 2294102300013 Isotopic ratios measured (number of atoms): 2294102300014 U-234/U-233 - 0.05168 +- 0.00010, 2294102300015 U-235/U-233 - 0.00303 +- 0.00007, 2294102300016 U-236/U-238 - 0.000184 +- 0.000020, 2294102300017 Th-232/U-233 - 67.93 +- 0.55 (0.8% standard deviation).2294102300018 MONITOR ((MONIT1)27-CO-59(N,G)27-CO-60,,SIG,,SPA) 2294102300019 ANALYSIS Effective cross sections were extracted using evaluated2294102300020 data of libraries and calculated neutron flux by 2294102300021 fitting simultaneously to experimental isotopic ratios,2294102300022 with the ROOT/MERCS code. 2294102300023 ERR-ANALYS (ERR-1,,2.) The normalization uncertainty (below 2%) 2294102300024 includes: 2294102300025 - Co-59 initial mass uncertainty 2294102300026 - Co-59(n,g)Co-60 cross section 2294102300027 - Co-60 half-life 2294102300028 - Co-60(n,g)Co-61 cross section 2294102300029 STATUS (TABLE) Table 1 of C,2009BUDA,81,2009. 2294102300030 Table 8 of J,NIM/A,591 (6.27+-0.18 b). 2294102300031 Table 2 of C,2007NICE. 2294102300032 Table 2 of R,INDC(NDS)-0574,85,2010 2294102300033 HISTORY (20090320A) Subent was added. 2294102300034 ENDBIB 32 0 2294102300035 NOCOMMON 0 0 2294102300036 DATA 5 1 2294102300037 EN-MEAN DATA DATA-ERR MONIT1 MONIT1-ERR 2294102300038 EV B B B B 2294102300039 0.0253 6.27 0.18 31. 1. 2294102300040 ENDDATA 3 0 2294102300041 ENDSUBENT 40 0 2294102399999 SUBENT 22941024 20160910 22542294102400001 BIB 4 9 2294102400002 REACTION (90-TH-232(N,G)90-TH-233,,SIG) 2294102400003 ANALYSIS 25.3 meV value was extracted from measured effective 2294102400004 cross section using the ratio of 25.3 meV c-s to 2294102400005 effective cross, calculated from data bases. 2294102400006 STATUS (TABLE) Table 1 of C,2009BUDA,81,2009. 2294102400007 Table 8 of J,NIM/A,591 (7.34+-0.21 b). 2294102400008 Table 2 of R,INDC(NDS)-0574,85,2010 2294102400009 (DEP,22941023) Spectrum average CS 2294102400010 HISTORY (20090320A) Subent was added. 2294102400011 ENDBIB 9 0 2294102400012 NOCOMMON 0 0 2294102400013 DATA 3 1 2294102400014 EN DATA DATA-ERR 2294102400015 EV B B 2294102400016 0.0253 7.34 0.21 2294102400017 ENDDATA 3 0 2294102400018 ENDSUBENT 17 0 2294102499999 SUBENT 22941025 20160910 22542294102500001 BIB 7 29 2294102500002 REACTION (91-PA-233(N,G)91-PA-234,,SIG,,SPA) 2294102500003 INC-SPECT Thermal Maxwellian flux.Neutron fluency was measured by2294102500004 Al-0.1%Co-59 monitor. Less 3% of neutrons have energy 2294102500005 greater 1 eV. Neutron flux in analysis was assumed to 2294102500006 be constant at (7.56+-0.23)[10**14 n/cm**2/s(measured).2294102500007 METHOD (MASSP) Precise mass spectrometry (Thermal Ionization 2294102500008 and Inductive Coupled Plasma Mass Spectrometry) 2294102500009 analysis after 43 day irradiation in V4 at 50 cm 2294102500010 distance from fuel element. 2294102500011 Isotopic ratios measured (number of atoms): 2294102500012 U-234/U-233 - 0.05168 +- 0.00010, 2294102500013 U-235/U-233 - 0.00303 +- 0.00007, 2294102500014 U-236/U-238 - 0.000184 +- 0.000020, 2294102500015 Th-232/U-233 - 67.93 +- 0.55 (0.8% standard deviation).2294102500016 ANALYSIS Effective cross sections were extracted using evaluated2294102500017 data of libraries and calculated neutron flux by 2294102500018 fitting simultaneously to experimental isotopic ratios,2294102500019 with the ROOT/MERCS code. 2294102500020 ERR-ANALYS (ERR-1,,2.) The normalization uncertainty (below 2%) 2294102500021 includes: 2294102500022 - Co-59 initial mass uncertainty 2294102500023 - Co-59(n,g)Co-60 cross section 2294102500024 - Co-60 half-life 2294102500025 - Co-60(n,g)Co-61 cross section 2294102500026 STATUS (TABLE) Table 1 of C,2009BUDA,81,2009. 2294102500027 Table 8 of J,NIM/A,591 . 2294102500028 Table 2 of C,2007NICE. 2294102500029 Table 2 of R,INDC(NDS)-0574,85,2010 2294102500030 HISTORY (20090320A) Subent was added. 2294102500031 ENDBIB 29 0 2294102500032 NOCOMMON 0 0 2294102500033 DATA 3 1 2294102500034 EN-MEAN DATA DATA-ERR 2294102500035 EV B B 2294102500036 0.0253 34.16 1.54 2294102500037 ENDDATA 3 0 2294102500038 ENDSUBENT 37 0 2294102599999 SUBENT 22941026 20160910 22542294102600001 BIB 4 9 2294102600002 REACTION (91-PA-233(N,G)91-PA-234,,SIG) 2294102600003 ANALYSIS 25.3 meV value was extracted from measured effective 2294102600004 cross section using the ratio of 25.3 meV c-s to 2294102600005 effective cross, calculated from data bases. 2294102600006 STATUS (TABLE) Table 1 of C,2009BUDA,81,2009. 2294102600007 Table 8 of J,NIM/A,591 . 2294102600008 Table 2 of R,INDC(NDS)-0574,85,2010 2294102600009 (DEP,22941025) 2294102600010 HISTORY (20090320A) Subent was added. 2294102600011 ENDBIB 9 0 2294102600012 NOCOMMON 0 0 2294102600013 DATA 3 1 2294102600014 EN DATA DATA-ERR 2294102600015 EV B B 2294102600016 0.0253 38.34 1.78 2294102600017 ENDDATA 3 0 2294102600018 ENDSUBENT 17 0 2294102699999 SUBENT 22941027 20160910 22542294102700001 BIB 7 29 2294102700002 REACTION (92-U-234(N,G)92-U-235,,SIG,,SPA) 2294102700003 INC-SPECT Thermal Maxwellian flux.Neutron fluency was measured by2294102700004 Al-0.1%Co-59 monitor. Less 3% of neutrons have energy 2294102700005 greater 1 eV. Neutron flux in analysis was assumed to 2294102700006 be constant at (7.56+-0.23)[10**14 n/cm**2/s(measured).2294102700007 METHOD (MASSP) Precise mass spectrometry (Thermal Ionization 2294102700008 and Inductive Coupled Plasma Mass Spectrometry) 2294102700009 analysis after 43 day irradiation in V4 at 50 cm 2294102700010 distance from fuel element. 2294102700011 Isotopic ratios measured (number of atoms): 2294102700012 U-234/U-233 - 0.05168 +- 0.00010, 2294102700013 U-235/U-233 - 0.00303 +- 0.00007, 2294102700014 U-236/U-238 - 0.000184 +- 0.000020, 2294102700015 Th-232/U-233 - 67.93 +- 0.55 (0.8% standard deviation).2294102700016 ANALYSIS Effective cross sections were extracted using evaluated2294102700017 data of libraries and calculated neutron flux by 2294102700018 fitting simultaneously to experimental isotopic ratios,2294102700019 with the ROOT/MERCS code. 2294102700020 ERR-ANALYS (ERR-1,,2.) The normalisation uncertainty (below 2%) 2294102700021 includes: 2294102700022 - Co-59 initial mass uncertainty 2294102700023 - Co-59(n,g)Co-60 cross section 2294102700024 - Co-60 half-life 2294102700025 - Co-60(n,g)Co-61 cross section 2294102700026 STATUS (TABLE) Table 1 of C,2009BUDA,81,2009. 2294102700027 Table 8 of J,NIM/A,591 . 2294102700028 Table 2 of C,2007NICE. 2294102700029 Table 2 of R,INDC(NDS)-0574,85,2010 2294102700030 HISTORY (20090320A) Subent was added. 2294102700031 ENDBIB 29 0 2294102700032 NOCOMMON 0 0 2294102700033 DATA 3 1 2294102700034 EN-MEAN DATA DATA-ERR 2294102700035 EV B B 2294102700036 0.0253 87.34 2.75 2294102700037 ENDDATA 3 0 2294102700038 ENDSUBENT 37 0 2294102799999 SUBENT 22941028 20160910 22542294102800001 BIB 4 9 2294102800002 REACTION (92-U-234(N,G)92-U-235,,SIG) 2294102800003 ANALYSIS 25.3 meV value was extracted from measured effective 2294102800004 cross section using the ratio of 25.3 meV c-s to 2294102800005 effective cross, calculated from data bases. 2294102800006 STATUS (TABLE) Table 1 of C,2009BUDA,81,2009. 2294102800007 Table 8 of J,NIM/A,591 . 2294102800008 Table 2 of R,INDC(NDS)-0574,85,2010 2294102800009 (DEP,22941027) 2294102800010 HISTORY (20090320A) Subent was added. 2294102800011 ENDBIB 9 0 2294102800012 NOCOMMON 0 0 2294102800013 DATA 3 1 2294102800014 EN DATA DATA-ERR 2294102800015 EV B B 2294102800016 0.0253 106.12 3.34 2294102800017 ENDDATA 3 0 2294102800018 ENDSUBENT 17 0 2294102899999 SUBENT 22941029 20160910 22542294102900001 BIB 7 29 2294102900002 REACTION (92-U-235(N,G)92-U-236,,SIG,,SPA) 2294102900003 INC-SPECT Thermal Maxwellian flux.Neutron fluency was measured by2294102900004 Al-0.1%Co-59 monitor. Less 3% of neutrons have energy 2294102900005 greater 1 eV. Neutron flux in analysis was assumed to 2294102900006 be constant at (7.56+-0.23)[10**14 n/cm**2/s(measured).2294102900007 METHOD (MASSP) Precise mass spectrometry (Thermal Ionization 2294102900008 and Inductive Coupled Plasma Mass Spectrometry) 2294102900009 analysis after 43 day irradiation in V4 at 50 cm 2294102900010 distance from fuel element. 2294102900011 Isotopic ratios measured (number of atoms): 2294102900012 U-234/U-233 - 0.05168 +- 0.00010, 2294102900013 U-235/U-233 - 0.00303 +- 0.00007, 2294102900014 U-236/U-238 - 0.000184 +- 0.000020, 2294102900015 Th-232/U-233 - 67.93 +- 0.55 (0.8% standard deviation).2294102900016 ANALYSIS Effective cross sections were extracted using evaluated2294102900017 data of libraries and calculated neutron flux by 2294102900018 fitting simultaneously to experimental isotopic ratios,2294102900019 with the ROOT/MERCS code. 2294102900020 ERR-ANALYS (ERR-1,,2.) The normalization uncertainty (below 2%) 2294102900021 includes: 2294102900022 - Co-59 initial mass uncertainty 2294102900023 - Co-59(n,g)Co-60 cross section 2294102900024 - Co-60 half-life 2294102900025 - Co-60(n,g)Co-61 cross section 2294102900026 STATUS (TABLE) Table 1 of C,2009BUDA,81,2009. 2294102900027 Table 8 of J,NIM/A,591 . 2294102900028 Table 2 of C,2007NICE. 2294102900029 Table 2 of R,INDC(NDS)-0574,85,2010 2294102900030 HISTORY (20090320A) Subent was added. 2294102900031 ENDBIB 29 0 2294102900032 NOCOMMON 0 0 2294102900033 DATA 3 1 2294102900034 EN-MEAN DATA DATA-ERR 2294102900035 EV B B 2294102900036 0.0253 79.01 9.05 2294102900037 ENDDATA 3 0 2294102900038 ENDSUBENT 37 0 2294102999999 SUBENT 22941030 20160910 22542294103000001 BIB 4 10 2294103000002 REACTION (92-U-235(N,G)92-U-236,,SIG) 2294103000003 ANALYSIS 25.3 meV value was extracted from measured effective 2294103000004 cross section using the ratio of 25.3 meV c-s to 2294103000005 effective cross, calculated from data bases. 2294103000006 STATUS (TABLE) Table 1 of C,2009BUDA,81,2009. 2294103000007 Table 8 of J,NIM/A,591 (98.15+-11.24 b) . 2294103000008 Table 2 of R,INDC(NDS)-0574,85,2010 2294103000009 (DEP,22941029) 2294103000010 HISTORY (20090320A) Subent was added. 2294103000011 (20120108A) Data were corrected as given in C,2009BUDA.2294103000012 ENDBIB 10 0 2294103000013 NOCOMMON 0 0 2294103000014 DATA 3 1 2294103000015 EN DATA DATA-ERR 2294103000016 EV B B 2294103000017 0.0253 98. 11. 2294103000018 ENDDATA 3 0 2294103000019 ENDSUBENT 18 0 2294103099999 SUBENT 22941031 20160910 22542294103100001 BIB 7 18 2294103100002 REACTION (93-NP-237(N,G)93-NP-238,,SIG,,MXW/FCT) 2294103100003 Maxwellian averaged cross-section multiplied by 2294103100004 sqrt(pi)/2 (as compared to the Westcott convention) 2294103100005 SAMPLE 13.82 microgram of Np-237, electrodeposited on Ti 2294103100006 backing, irradiated 2 hours in H9 channel. 2294103100007 ANALYSIS Effective cross sections were extracted by evaluated 2294103100008 data of libraries and calculated neutron flux. 2294103100009 METHOD (GSPEC) Alpha and gamma spectroscopy on H9 channel. 2294103100010 (ASPEC) 2294103100011 INC-SPECT Thermal Maxwellian . 2294103100012 STATUS (TABLE) Table 3 of C,2009BUDA,81,2009 (151+-4 b) . 2294103100013 Table 3 of C,2007NICE. 2294103100014 Table 2 of C,2007CORSEN. 2294103100015 Table 3 of R,INDC(NDS)-0574,85,2010 2294103100016 (SPSDD,23100002) Superseded by newer data in 23100.002.2294103100017 HISTORY (20090320A) Subent was added. 2294103100018 (20100327A) Data were superseded. 2294103100019 (20160910A) Data were re-stored. 2294103100020 ENDBIB 18 0 2294103100021 NOCOMMON 0 0 2294103100022 DATA 3 1 2294103100023 EN-MEAN DATA DATA-ERR 2294103100024 EV B B 2294103100025 0.0253 150. 4.2 2294103100026 ENDDATA 3 0 2294103100027 ENDSUBENT 26 0 2294103199999 SUBENT 22941032 20160910 22542294103200001 BIB 4 13 2294103200002 REACTION (93-NP-237(N,G)93-NP-238,,SIG) 2294103200003 ANALYSIS 25.3 meV value was extracted from measured effective 2294103200004 cross section using the ratio of 25.3 meV c-s to 2294103200005 effective cross, calculated from data bases. 2294103200006 STATUS (TABLE) Table 3 of C,2009BUDA,81,2009 (182+-4.5 b) . 2294103200007 Table 3 of C,2007NICE. 2294103200008 Table 2 of C,2007CORSEN . 2294103200009 Table 3 of R,INDC(NDS)-0574,85,2010 2294103200010 (DEP,22941031) 2294103200011 (SPSDD,23100003) Superseded by newer data in 23100.003.2294103200012 HISTORY (20090320A) Subent was added. 2294103200013 (20100327A) Data were superseded. 2294103200014 (20160910A) Data were re-stored. 2294103200015 ENDBIB 13 0 2294103200016 NOCOMMON 0 0 2294103200017 DATA 3 1 2294103200018 EN DATA DATA-ERR 2294103200019 EV B B 2294103200020 0.0253 180. 5. 2294103200021 ENDDATA 3 0 2294103200022 ENDSUBENT 21 0 2294103299999 SUBENT 22941033 20160910 22542294103300001 BIB 6 13 2294103300002 REACTION (93-NP-238(N,F),,SIG,,SPA) 2294103300003 SAMPLE Np-237 deposit of (42+-1.3) microgram in V4 channel 2294103300004 using TDFC , irradiated 43 days. 2294103300005 ANALYSIS Effective cross sections were extracted by evaluated 2294103300006 data of libraries and calculated neutron flux. 2294103300007 INC-SPECT Thermal Maxwellian. 2294103300008 STATUS (TABLE) Table 3 of C,2009BUDA,81,2009. 2294103300009 Table 3 of C,2007NICE (1828.+-55.) . 2294103300010 Table 2 of C,2007CORSEN . 2294103300011 Table 3 of R,INDC(NDS)-0574,85,2010 2294103300012 (PRELM) Preliminary data. 2294103300013 HISTORY (20090320A) Subent was added. 2294103300014 (20120108A) Data were corrected as given in C,2009BUDA.2294103300015 ENDBIB 13 0 2294103300016 NOCOMMON 0 0 2294103300017 DATA 3 1 2294103300018 EN-MEAN DATA DATA-ERR 2294103300019 EV B B 2294103300020 0.0253 1611. 100. 2294103300021 ENDDATA 3 0 2294103300022 ENDSUBENT 21 0 2294103399999 SUBENT 22941034 20160910 22542294103400001 BIB 5 16 2294103400002 REACTION (93-NP-238(N,F),,SIG) 2294103400003 REL-REF (A,41324002,S.Abramovich+,C,95OBNIN,,303,199510) 2294103400004 Agree with data of S.Abramovich+ (2110 +- 740 b) . 2294103400005 (D,13602008,Y.Danon+,J,NSE,124,482,1996) 2294103400006 Less than data of Y.Danon+ (2638 +- 58 b) . 2294103400007 ANALYSIS 25.3 meV value was extracted from measured effective 2294103400008 cross section using the ratio of 25.3 meV c-s to 2294103400009 effective cross, calculated from data bases. 2294103400010 STATUS (TABLE) Table 3 of C,2009BUDA,81,2009. 2294103400011 Table 3 of C,2007NICE (2165.+-70. b). 2294103400012 Table 2 of C,2007CORSEN . 2294103400013 Table 3 of R,INDC(NDS)-0574,85,2010 2294103400014 (DEP,22941033) 2294103400015 (PRELM) Preliminary data. 2294103400016 HISTORY (20090320A) Subent was added. 2294103400017 (20120108A) Data were corrected as given in C,2009BUDA.2294103400018 ENDBIB 16 0 2294103400019 NOCOMMON 0 0 2294103400020 DATA 3 1 2294103400021 EN DATA DATA-ERR 2294103400022 EV B B 2294103400023 0.0253 2050. 110. 2294103400024 ENDDATA 3 0 2294103400025 ENDSUBENT 24 0 2294103499999 SUBENT 22941035 20160910 22542294103500001 BIB 7 13 2294103500002 REACTION (94-PU-238(N,G)94-PU-239,,SIG,,SPA) 2294103500003 SAMPLE Np-237 deposit of (42+-1.3) microgram in V4 channel 2294103500004 using TDFC , irradiated 43 days. 2294103500005 ANALYSIS Effective cross sections were extracted by evaluated 2294103500006 data of libraries and calculated neutron flux. 2294103500007 COMMENT Of authors. Will be measured again. 2294103500008 INC-SPECT Thermal Maxwellian . 2294103500009 STATUS (TABLE) Table 3 of C,2009BUDA,81,2009. 2294103500010 Table 3 of C,2007NICE (388.+-12. b). 2294103500011 Table 3 of R,INDC(NDS)-0574,85,2010 2294103500012 (PRELM) Preliminary data. 2294103500013 HISTORY (20090320A) Subent was added. 2294103500014 (20120108A) Data were corrected as given in C,2009BUDA.2294103500015 ENDBIB 13 0 2294103500016 NOCOMMON 0 0 2294103500017 DATA 3 1 2294103500018 EN-MEAN DATA DATA-ERR 2294103500019 EV B B 2294103500020 0.0253 411. 20. 2294103500021 ENDDATA 3 0 2294103500022 ENDSUBENT 21 0 2294103599999 SUBENT 22941036 20160910 22542294103600001 BIB 4 11 2294103600002 REACTION (94-PU-238(N,G)94-PU-239,,SIG) 2294103600003 ANALYSIS 25.3 meV value was extracted from measured effective 2294103600004 cross section using the ratio of 25.3 meV c-s to 2294103600005 effective cross, calculated from data bases. 2294103600006 STATUS (TABLE) Table 3 of C,2009BUDA,81,2009. 2294103600007 Table 3 of C,2007NICE (476.+-33. b) . 2294103600008 Table 3 of R,INDC(NDS)-0574,85,2010 2294103600009 (PRELM) Preliminary data. 2294103600010 (DEP,22941035) 2294103600011 HISTORY (20090320A) Subent was added. 2294103600012 (20120108A) Data were corrected as given in C,2009BUDA.2294103600013 ENDBIB 11 0 2294103600014 NOCOMMON 0 0 2294103600015 DATA 3 1 2294103600016 EN DATA DATA-ERR 2294103600017 EV B B 2294103600018 0.0253 514. 21. 2294103600019 ENDDATA 3 0 2294103600020 ENDSUBENT 19 0 2294103699999 SUBENT 22941037 20160910 22542294103700001 BIB 7 16 2294103700002 REACTION (96-CM-244(N,G)96-CM-245,,SIG,,SPA) 2294103700003 SAMPLE 39.46+-0.4 microgram of curium. Cm-244 - 66.9% (26.4+-2294103700004 0.44 microg), Cm-245 -3.8% (1.539+-0.027 microg), 2294103700005 Pu-240 -23.6% . And 4.22+-0.004 microg of U-235. 2294103700006 Irradiation in V4 channel,25cm above the median plane.2294103700007 Measured by TDFC. 2294103700008 ANALYSIS Effective cross sections were extracted by evaluated 2294103700009 data of libraries and calculated neutron flux. 2294103700010 INC-SPECT Thermal Maxwellian . 2294103700011 ERR-ANALYS (ERR-1,,1.) Error of isotopic concentration less 1.% . 2294103700012 STATUS (TABLE) Table 5 of C,2009BUDA,81,2009. 2294103700013 Table 5 of C,2007NICE (28.7+-3.4 b) . 2294103700014 Table 4 of R,INDC(NDS)-0574,85,2010 2294103700015 (PRELM) Preliminary data. 2294103700016 HISTORY (20090320A) Subent was added. 2294103700017 (20120108A) Data were corrected as given in C,2009BUDA.2294103700018 ENDBIB 16 0 2294103700019 NOCOMMON 0 0 2294103700020 DATA 3 1 2294103700021 EN-MEAN DATA DATA-ERR 2294103700022 EV B B 2294103700023 0.0253 19.11 2.67 2294103700024 ENDDATA 3 0 2294103700025 ENDSUBENT 24 0 2294103799999 SUBENT 22941038 20160910 22542294103800001 BIB 4 11 2294103800002 REACTION (96-CM-244(N,G)96-CM-245,,SIG) 2294103800003 ANALYSIS 25.3 meV value was extracted from measured effective 2294103800004 cross section using the ratio of 25.3 meV c-s to 2294103800005 effective cross, calculated from data bases. 2294103800006 STATUS (TABLE) Table 5 of C,2009BUDA,81,2009. 2294103800007 Table 3 of C,2007NICE (20.8+-2.5 b ). 2294103800008 Table 4 of R,INDC(NDS)-0574,85,2010 2294103800009 (DEP,22941037) 2294103800010 (PRELM) Preliminary data. 2294103800011 HISTORY (20090320A) Subent was added. 2294103800012 (20120108A) Data were corrected as given in C,2009BUDA.2294103800013 ENDBIB 11 0 2294103800014 NOCOMMON 0 0 2294103800015 DATA 3 1 2294103800016 EN DATA DATA-ERR 2294103800017 EV B B 2294103800018 0.0253 15.81 3. 2294103800019 ENDDATA 3 0 2294103800020 ENDSUBENT 19 0 2294103899999 SUBENT 22941039 20160910 22542294103900001 BIB 7 20 2294103900002 REACTION (96-CM-245(N,F),,SIG,,SPA) 2294103900003 SAMPLE 39.46+-0.4 microgram of curium. Cm-244 - 66.9% (26.4+-2294103900004 0.44 microg), Cm-245 -3.8% (1.539+-0.027 microg), 2294103900005 Pu-240 -23.6% . And 4.22+-0.004 microg of U-235. 2294103900006 Irradiation in V4 channel,25cm above the median plane.2294103900007 Measured by TDFC. 2294103900008 ANALYSIS Effective cross sections were extracted by evaluated 2294103900009 data of libraries and calculated neutron flux. 2294103900010 INC-SPECT Thermal Maxwellian. 2294103900011 ERR-ANALYS (ERR-1,,1.) Error of isotopic concentration less 1.% . 2294103900012 STATUS (TABLE) Table 5 of C,2009BUDA,81,2009. 2294103900013 Text of C,2007CORSEN, item 4.3 . 2294103900014 Table 4 of R,INDC(NDS)-0574,85,2010 2294103900015 Preliminary data (1400.+-29.b) are given in Table 5 2294103900016 of C,2007NICE. 2294103900017 HISTORY (20090320A) Subent was added. 2294103900018 (20090911A) M.M. Data of C,2007NICE were changed into 2294103900019 newer data of 2007CORSEN. PRELM was deleted. 2294103900020 (20151216A) SD: SF4 deleted from REACTION code 2294103900021 following publication (remark from E.Dupont). 2294103900022 ENDBIB 20 0 2294103900023 NOCOMMON 0 0 2294103900024 DATA 3 1 2294103900025 EN-MEAN DATA DATA-ERR 2294103900026 EV B B 2294103900027 0.0253 1352. 23. 2294103900028 ENDDATA 3 0 2294103900029 ENDSUBENT 28 0 2294103999999 SUBENT 22941040 20160910 22542294104000001 BIB 5 23 2294104000002 REACTION (96-CM-245(N,F),,SIG) 2294104000003 REL-REF (A,40467020,V.D.Gavrilov+,J,SJA,41,808,1976) 2294104000004 Agree with data of Gavrilov+ (1900+-100 b). 2294104000005 (A,10128004,R.W.Benjamin+,J,NSE,47,203,1972) 2294104000006 Agree with data of C.C.Benjzmin+ (2018+-37 b) . 2294104000007 (D,10730005,J.C.Browne+,J,NSE,65,166,1978) 2294104000008 About 10 % less than data of C.C.Browne+ (2143+-58 b).2294104000009 ANALYSIS 25.3 meV value was extracted from measured effective 2294104000010 cross section using the ratio of 25.3 meV c-s to 2294104000011 effective cross, calculated from data bases. 2294104000012 STATUS (TABLE) Table 5 of C,2009BUDA,81,2009. 2294104000013 Text of C,2007CORSEN, item 4.3 (1943.+-65. b) . 2294104000014 Table 4 of R,INDC(NDS)-0574,85,2010 2294104000015 (PRELM) Preliminary data. 2294104000016 (DEP,22941039) 2294104000017 Preliminary data (2012.+-61.b) are given in Table 5 2294104000018 of C,2007NICE. 2294104000019 HISTORY (20090320A) Subent was added. 2294104000020 (20090911A) M.M. Data of C,2007NICE were changed into 2294104000021 newer data of 2007CORSEN. PRELM was deleted. 2294104000022 (20120108A) Data were corrected as given in C,2009BUDA.2294104000023 (20151216A) SD: SF4 deleted from REACTION code 2294104000024 following publication (remark from E.Dupont). 2294104000025 ENDBIB 23 0 2294104000026 NOCOMMON 0 0 2294104000027 DATA 3 1 2294104000028 EN DATA DATA-ERR 2294104000029 EV B B 2294104000030 0.0253 1979. 65. 2294104000031 ENDDATA 3 0 2294104000032 ENDSUBENT 31 0 2294104099999 SUBENT 22941041 20120108 22302294104100001 BIB 4 14 2294104100002 REACTION (95-AM-241(N,G)95-AM-242-G/T,,SIG/RAT) 2294104100003 Isomeric branching ratio. 2294104100004 ANALYSIS 25.3 meV point branching ratio was derived from 2294104100005 branching ratio measured in Maxwellian incident neutron2294104100006 spectrum. The same values are given as for Maxwellian 2294104100007 spectrum as for 25.3 meV point in Table 3 of 2294104100008 C,2007CORSEN. 2294104100009 STATUS (TABLE) Table 3 of 2009BUDA. 2294104100010 Table 3 of C,2007CORSEN . 2294104100011 Table 4 of C,2007NICE (0.8947+-0.0038). 2294104100012 (DEP,22941012) 2294104100013 HISTORY (20090911C) M.M. Subent added . 2294104100014 (20120108A) Error was corrected 0.004 -> 0.0038 as 2294104100015 given in C,2009BUDA. 2294104100016 ENDBIB 14 0 2294104100017 NOCOMMON 0 0 2294104100018 DATA 3 1 2294104100019 EN DATA DATA-ERR 2294104100020 EV NO-DIM NO-DIM 2294104100021 0.0253 0.8947 0.0038 2294104100022 ENDDATA 3 0 2294104100023 ENDSUBENT 22 0 2294104199999 SUBENT 22941042 20151216 22462294104200001 BIB 5 9 2294104200002 REACTION (98-CF-249(N,G)98-CF-250,,SIG,,SPA) 2294104200003 SAMPLE No information. 2294104200004 ANALYSIS Effective cross sections were extracted by evaluated 2294104200005 data of libraries and calculated neutron flux. 2294104200006 STATUS (TABLE) Table 5 of C,2009BUDA,81,2009. 2294104200007 (PRELM) Preliminary data. 2294104200008 HISTORY (20120108C) Subent was added. 2294104200009 (20151216A) SD: REACTION code changed: Cm-245(n,f) -> 2294104200010 Cf-249(n,g)Cf-250 following Tbl.5 of C,2009BUDA,81,20092294104200011 ENDBIB 9 0 2294104200012 NOCOMMON 0 0 2294104200013 DATA 3 1 2294104200014 EN-MEAN DATA DATA-ERR 2294104200015 EV B B 2294104200016 0.0253 309. 8. 2294104200017 ENDDATA 3 0 2294104200018 ENDSUBENT 17 0 2294104299999 SUBENT 22941043 20151216 22462294104300001 BIB 4 10 2294104300002 REACTION (98-CF-249(N,G)98-CF-250,,SIG) 2294104300003 ANALYSIS 25.3 meV value was extracted from measured effective 2294104300004 cross section using the ratio of 25.3 meV c-s to 2294104300005 effective cross, calculated from data bases. 2294104300006 STATUS (TABLE) Table 5 of C,2009BUDA,81,2009. 2294104300007 (PRELM) Preliminary data. 2294104300008 (DEP,22941042) 2294104300009 HISTORY (20120108C) Subent was added. 2294104300010 (20151216A) SD: REACTION code changed: Cm-245(n,f) -> 2294104300011 Cf-249(n,g)Cf-250 following Tbl.5 of C,2009BUDA,81,20092294104300012 ENDBIB 10 0 2294104300013 NOCOMMON 0 0 2294104300014 DATA 3 1 2294104300015 EN DATA DATA-ERR 2294104300016 EV B B 2294104300017 0.0253 384. 10. 2294104300018 ENDDATA 3 0 2294104300019 ENDSUBENT 18 0 2294104399999 SUBENT 22941044 20200909 22912294104400001 BIB 8 12 2294104400002 REACTION (95-AM-243(N,G)95-AM-244,,SIG,,SPA) 2294104400003 INC-SOURCE H9 channel. 2294104400004 SAMPLE Am-243 10.926+-0.14 microgram was electrodeposited on 2294104400005 the Ni backing. 2294104400006 METHOD (ACTIV) Irradiated during 3.277+-0.002 hr. 2294104400007 RAD-DET (96-CM-244,A) 2294104400008 COMMENT A.Letourneau (2020-07-21): 74.1 b is the averaged cross2294104400009 section and not the 2200 m/s value. 2294104400010 STATUS (TABLE) Text, page 90 of R,INDC(NDS)-0574,85,2010 2294104400011 (COREL,22924002) Measurement with different sample. 2294104400012 HISTORY (20160910C) Subent was added. 2294104400013 (20200909U) SD: Comment from author added. 2294104400014 ENDBIB 12 0 2294104400015 NOCOMMON 0 0 2294104400016 DATA 3 1 2294104400017 EN-MEAN DATA DATA-ERR 2294104400018 EV B B 2294104400019 0.0253 73.8 2.3 2294104400020 ENDDATA 3 0 2294104400021 ENDSUBENT 20 0 2294104499999 SUBENT 22941045 20160910 22542294104500001 BIB 7 12 2294104500002 REACTION (95-AM-243(N,G)95-AM-244-G/T,,SIG/RAT,,SPA) 2294104500003 INC-SOURCE H9 channel . 2294104500004 SAMPLE Am-243 10.926+-0.14 mirogram was electrodeposited on 2294104500005 the Ni backing . 2294104500006 METHOD (ACTIV) Irradiated during 3.277+-0.002 hr to measure 2294104500007 total capture cross section. Then irradiated during 2294104500008 24.00+-0.02 min more to measure the decay half-lives of2294104500009 244mAm and 244gAm isotopes and the branching ratio. 2294104500010 DECAY-DATA (95-AM-244-G,10.65HR) 10.65+-0.12 hr. 2294104500011 (95-AM-244-M,28.25MIN) 28.25+-1.3 min. 2294104500012 STATUS (TABLE) Text, page 90 of R,INDC(NDS)-0574,85,2010 2294104500013 HISTORY (20160910C) Subent was added. 2294104500014 ENDBIB 12 0 2294104500015 NOCOMMON 0 0 2294104500016 DATA 3 1 2294104500017 EN-MEAN DATA DATA-ERR 2294104500018 EV NO-DIM NO-DIM 2294104500019 0.0253 0.0474 0.0001 2294104500020 ENDDATA 3 0 2294104500021 ENDSUBENT 20 0 2294104599999 ENDENTRY 45 0 2294199999999