ENTRY 23140 20150707 22442314000000001 SUBENT 23140001 20150707 22442314000100001 BIB 16 72 2314000100002 TITLE Measurements of neutron capture cross sections of 2314000100003 palladium isotopes at the J-PARC/MLF/ANNRI . 2314000100004 AUTHOR (S.Nakamura, K.Furutaka, S.Goko,H.Harada,J.Hori, 2314000100005 M.Igashira,T.Kamiyama, T.Katabuchi, A.Kimura,T.Kin, 2314000100006 K.Kino,F.Kitatani,Y.Kiyanagi,M.Koizumi,M.Mizumoto, 2314000100007 M.Ohta,M.Oshima,Y.Toh,T.Fujii,S.Fukutani,K.Takamiya, 2314000100008 K.Y.Hara, K.Hirose,F.Hiraga,S.Fukutani) 2314000100009 INSTITUTE (2JPNJAE) S.Nakamura, K.Furutaka, S.Goko, H.Harada, 2314000100010 A.Kimura,T.Kin,F.Kitatani,M.Koizumi,M.Ohta,M.Oshima, 2314000100011 Y.Toh,K.Y.Hara,K.Hirose 2314000100012 (2JPNKTO) J.Hori,T.Fujii,S.Fukutani,K.Takamiya, 2314000100013 S.Fukutani. 2314000100014 (2JPNTIT) M.Igashira, T.Katabuchi,M.Mizumoto. 2314000100015 (2JPNHOK) Hokkaido University, Kita 13, Nishi 8, 2314000100016 Kita-ku, Sapporo, 060-8628, Japan- S.Goko,T.Kamiyama, 2314000100017 K.Kino,Y.Kiyanagi,F.Hiraga. 2314000100018 (2JPNKEK) K.Kino. 2314000100019 (2JPNOSA) M.Ohta. 2314000100020 REFERENCE (J,KPS,59,1773,2011) ND2010 Conf.Proc. paper #1295, 2314000100021 in ND2010 Abstract book, page 214. 2314000100022 (J,NDS,119,143,2014) ND2014 . 2314000100023 #doi:10.1016/j.nds.2014.08.040 2314000100024 (S,JAEA-C-2012-001,159,2012) 2314000100025 Preliminary data for Pd-107. 2314000100026 FACILITY (SYNCH,2JPNJAE) Exp.apparatus "Accurate Neutron-Nucleus2314000100027 Reaction measurement Instrument (ANNRI)" in Material 2314000100028 and Life science exp. Facility (MLF) at the Japan 2314000100029 Proton Accelerator Research Complex (J-PARC). 2314000100030 Beam line No 4 - BL04. 2314000100031 37.5 mm Pb filter was placed to suppress the gamma 2314000100032 flash. 2314000100033 Beam size was collimated to 3 mm diameter at the 2314000100034 sample position with a rotary collimator. 2314000100035 INC-SOURCE (SPALL) 2314000100036 DETECTOR (D4PI,GE,BGO) 4Pi Ge spectrometer: two cluster-Ge 2314000100037 detectors and BGO compton suppression detectors. 2314000100038 METHOD (TOF) TOF spectra of Pd - 105, 106, 107, 108 were 2314000100039 measured. 2314000100040 SAMPLE Pd-107 sample was supplied by the Nuclear Research and 2314000100041 consultancy Group (NRG), Netherlands; was reanalyzed in2314000100042 detail by a mass spectroscopy at the Kyoto University 2314000100043 Research Reactor Institute. 2314000100044 Pd-107 sample - pellet of 137.37 mg weight, 4.523 mm 2314000100045 diameter, 0.917 mm thickness; was packed in an Al 2314000100046 container of 229.76 mg weight, 9.077 mm diameter, 2314000100047 1.86 mm thickness. 2314000100048 Another Al container - for background. 2314000100049 Pd samples were set at the position of 21.5m from the 2314000100050 MLF neutron source with a 120-kW power (25 Hz). 2314000100051 PART-DET (G) Gamma-rays from neutron capture. 2314000100052 CORRECTION For dead time - correction factor was obtained by using2314000100053 the random pulse generator. 2314000100054 For self-shielding and multi-scattering effects by 2314000100055 the Monte Carlo simulation code MCNP. 2314000100056 MONITOR 1(5-B-10(N,A)3-LI-7,,SIG) 2314000100057 The TOF spectrum corresponding to the flux of neutrons 2314000100058 was derived by gating on the 478-keV gamma ray emitted 2314000100059 through the 10B(n, a g)7Li reaction. 2314000100060 2(5-B-10(N,G)5-B-11,,SIG) 2314000100061 Neutron flux was deduced from the gated TOF spectrum 2314000100062 and the neuron-capture cross sections of B-10 in 2314000100063 JENDL-3.3. 2314000100064 MONIT-REF 2(,,3,JENDL-4.0,,2010) 2314000100065 DECAY-MON 1(3-LI-7-L,,DG,478.) 2314000100066 COMMENT This work was supported by JSPS KAKENHI Grant 22226016.2314000100067 HISTORY (20110801C) M.M. 2314000100068 (20121016A) M.M. Reference S,JAEA-C-2012-001,159,2012 2314000100069 was added. Subents 004-006 were added. 2314000100070 BIB information was updated. 2314000100071 (20150707U) M.M. Ref. for J,NDS,119,143,2014 was added.2314000100072 Authors K.Y.Hara, K.Hirose,F.Hiraga,S.Fukutani added. 2314000100073 BIB information was added in Subents 005,006 . 2314000100074 ENDBIB 72 0 2314000100075 NOCOMMON 0 0 2314000100076 ENDSUBENT 75 0 2314000199999 SUBENT 23140002 20121016 22332314000200001 BIB 4 20 2314000200002 REACTION (46-PD-105(N,G)46-PD-106,,SIG) 2314000200003 SAMPLE Pd-107 sample isotope abundance (%): 2314000200004 Pd-102 - 0.0, Pd-104 - 1.75, Pd-105 - 48.5, 2314000200005 Pd-106 - 23.0, Pd-107 - 15.3, Pd-108 - 8.75, 2314000200006 Pd-109 - 2.80. 2314000200007 Enriched samples of Pd-108 (99.5%) and Pd-106 (95.96%) 2314000200008 of weights 52.7 mg and 34.7 mg, respectively. 2314000200009 ANALYSIS TOF spectrum owing to the Pd-105(n,gamma) reaction was 2314000200010 carefully extracted by gating on 512-keV ground-state 2314000200011 transition gamma-ray in the pulse-height spectrum of 2314000200012 Pd-107. 2314000200013 Relative neutron capture cross sections of Pd-105 2314000200014 were derived from the neutron flux and the net TOF 2314000200015 spectrum. Relative cross sections were normalized to 2314000200016 the value of JENDL-3.3 at 1 eV. 2314000200017 STATUS (PRELM) Preliminary data on Fig.8 of J,KPS,(1295),2011.2314000200018 Preliminary results - some contributions of 2314000200019 impurities, Pd-108 and Pd-107, remain in the energy 2314000200020 region of several eV, it is necessary to examine how to2314000200021 reject the contributions. 2314000200022 ENDBIB 20 0 2314000200023 NOCOMMON 0 0 2314000200024 NODATA 0 0 2314000200025 ENDSUBENT 24 0 2314000299999 SUBENT 23140003 20121016 22332314000300001 BIB 7 33 2314000300002 REACTION (46-PD-107(N,G)46-PD-108,,SIG) 2314000300003 SAMPLE Pd-107 sample isotope abundance (%): 2314000300004 Pd-102 - 0.0, Pd-104 - 1.75, Pd-105 - 48.5, 2314000300005 Pd-106 - 23.0, Pd-107 - 15.3, Pd-108 - 8.75, 2314000300006 Pd-109 - 2.80. 2314000300007 Enriched samples of Pd-108 (99.5%) and Pd-106 (95.96%) 2314000300008 of weights 52.7 mg and 34.7 mg, respectively. 2314000300009 DECAY-DATA (46-PD-106-L,,DG,512.) 2314000300010 (46-PD-107,6.5E+6YR) 2314000300011 ANALYSIS To derive the relative neutron-capture cross sections 2314000300012 of Pd-107, net TOF component of Pd-107 was extracted 2314000300013 simply by subtracting the TOF spectrum of Pd-105 from 2314000300014 TOF spectrum obtained with the 107Pd sample. 2314000300015 Then the relative cross sections were normalized at 2314000300016 the third resonance peak with the value of JENDL-3.3. 2314000300017 REL-REF (A,14133002,S.Nakamura+,J,NST,44,103,2007) 2314000300018 These data agree with lower limit (9.16 +- 0.27 b) of 2314000300019 the thermal-neutron capture cross section from 2314000300020 J,NST,44,103,2007. 2314000300021 COMMENT Of compiler M.M. C-S value of REL-REF is given in 2314000300022 J,KPS,(1295),2011 as 9.6 b by misprint, correct value 2314000300023 as given in REL-REF - 9.16 b. 2314000300024 STATUS (PRELM) Preliminary data on Fig.9 of J,KPS,(1295),2011.2314000300025 Some contributions due to other Pd isotopes (e.g.108Pd)2314000300026 remain in the resonance region, because it was 2314000300027 difficult to get rid of contributions due to the 2314000300028 impurities by the simple subtraction done in the 2314000300029 present study. 2314000300030 There is a possibility that the thermal c-s would be 2314000300031 about five times large compared with the evaluated one 2314000300032 of JENDL-3.3 - 2.007 b. 2314000300033 (SPSDD,23140004) Superseded by newer publication, 2314000300034 see Subent 004. 2314000300035 ENDBIB 33 0 2314000300036 NOCOMMON 0 0 2314000300037 NODATA 0 0 2314000300038 ENDSUBENT 37 0 2314000399999 SUBENT 23140004 20121016 22332314000400001 BIB 5 34 2314000400002 REACTION (46-PD-107(N,G)46-PD-108,,SIG) 2314000400003 SAMPLE Pd-107 sample isotope abundance (%): 2314000400004 Pd-102 - 0.0, Pd-104 - 1.6+-0.4, Pd-105 - 48.8+-0.8, 2314000400005 Pd-106 - 23.1+-0.3, Pd-107 - 15.3+-0.4, 2314000400006 Pd-108 - 8.7+-0.3, Pd-109 - 2.6+-0.3. 2314000400007 ANALYSIS The neutron capture cross sections involving the 2314000400008 contributions of both 107Pd and other Pd isotopes were 2314000400009 derived in the energy range from 0.01 eV to 300 eV from2314000400010 the obtained TOF spectra relative to the cross sections2314000400011 of 10B. The relative cross sections were normalized to 2314000400012 the values calculated by the SAMMY code with JENDL-4.0 2314000400013 at the three energy points: 6.8 eV of 107Pd, 11.8 eV of2314000400014 105Pd, and 33 eV of 108Pd. 2314000400015 The cross sections of 107Pd in the low energy region 2314000400016 were derived as follows: 2314000400017 - the cross sections of Pd isotopes except for 107Pd 2314000400018 were calculated with the resonance parameters in 2314000400019 JENDL-4.0, 2314000400020 - the cross-section components for those Pd isotopes 2314000400021 were subtracted from the result for sample, 2314000400022 - the remained components were divided by the abundance2314000400023 of 107Pd in the sample. 2314000400024 REL-REF (A,14133002,S.Nakamura+,J,NST,44,103,2007) 2314000400025 The obtained cross-section curve in the thermal energy 2314000400026 region supports the previous result. 2314000400027 STATUS (PRELM) 2314000400028 On Fig.2 of S,JAEA-C-2012-001,159,2012 - capture c-s 2314000400029 for sample, energy range from 1 to 100 eV. 2314000400030 On Fig. 5 of S,JAEA-C-2012-001,159,2012 - capture c-s 2314000400031 for Pd-107, energy range from 0.01 to 10 eV . 2314000400032 Request for the data was not send, because data of c-s2314000400033 are still preliminary, "in near future, final result 2314000400034 for Pd-107 c-s will be published" - page 152 of 2314000400035 S,JAEA-C-2012-001,159,2012. 2314000400036 ENDBIB 34 0 2314000400037 NOCOMMON 0 0 2314000400038 NODATA 0 0 2314000400039 ENDSUBENT 38 0 2314000499999 SUBENT 23140005 20150707 22442314000500001 BIB 6 15 2314000500002 REACTION (46-PD-107(N,EL),,WID) Neutron width 2314000500003 SAMPLE Pd-107 sample isotope abundance (%): 2314000500004 Pd-102 - 0.0, Pd-104 - 1.6+-0.4, Pd-105 - 48.8+-0.8, 2314000500005 Pd-106 - 23.1+-0.3, Pd-107 - 15.3+-0.4, 2314000500006 Pd-108 - 8.7+-0.3, Pd-109 - 2.6+-0.3. 2314000500007 ANALYSIS The neutron width was obtained by peak-fitting of the 2314000500008 present data with the SAMMY code. 2314000500009 COMMENT Of authors. 2314000500010 The value in JENDL-4.0 is 0.01 meV, which is about five2314000500011 times larger than the present result. 2314000500012 We found that both the 3.9-eV and 5.2-eV resonances do 2314000500013 not belong to 107Pd. 2314000500014 ERR-ANALYS (DATA-ERR) Not specified. 2314000500015 STATUS (PRELM) Text, page 150 of S,JAEA-C-2012-001,159,2012. 2314000500016 (TABLE) Text,page 145 of J,NDS,119,143,2014 2314000500017 ENDBIB 15 0 2314000500018 NOCOMMON 0 0 2314000500019 DATA 3 1 2314000500020 EN-RES DATA DATA-ERR 2314000500021 EV MILLI-EV MILLI-EV 2314000500022 2.9 0.0018 0.0001 2314000500023 ENDDATA 3 0 2314000500024 ENDSUBENT 23 0 2314000599999 SUBENT 23140006 20150707 22442314000600001 BIB 4 9 2314000600002 REACTION (46-PD-107(N,G)46-PD-108,,SIG) 2314000600003 SAMPLE Pd-107 sample isotope abundance (%): 2314000600004 Pd-102 - 0.0, Pd-104 - 1.6+-0.4, Pd-105 - 48.8+-0.8, 2314000600005 Pd-106 - 23.1+-0.3, Pd-107 - 15.3+-0.4, 2314000600006 Pd-108 - 8.7+-0.3, Pd-109 - 2.6+-0.3. 2314000600007 ANALYSIS Thermal point c-s was defined from the behavior of the 2314000600008 cross sections. 2314000600009 STATUS (PRELM) Text, page 151 of S,JAEA-C-2012-001,159,2012. 2314000600010 (TABLE) Text,page 146 and on Fig.6 of NDS,119,143,2014 2314000600011 ENDBIB 9 0 2314000600012 NOCOMMON 0 0 2314000600013 DATA 2 1 2314000600014 EN DATA-APRX 2314000600015 EV B 2314000600016 0.0253 10. 2314000600017 ENDDATA 3 0 2314000600018 ENDSUBENT 17 0 2314000699999 ENDENTRY 6 0 2314099999999