ENTRY 23181 20180909 22712318100000001 SUBENT 23181001 20180909 22712318100100001 BIB 10 37 2318100100002 AUTHOR (J.Lee, J.Hori, K.Nakajima, T.Sano, S.Lee) 2318100100003 TITLE Neutron capture cross section measurements of 151, 2318100100004 153Eu using a pair of C6D6 detectors. 2318100100005 REFERENCE (J,NST,54,1046,2017) 2318100100006 #doi:10.1080/00223131.2017.1344575 2318100100007 Main reference 2318100100008 (S,JAEA-C-2011-002,101,2011) 2318100100009 Preliminary data on graphs. 2318100100010 INSTITUTE (2JPNKTO,3KORDAU) 2318100100011 FACILITY (LINAC,2JPNKTO) Kyoto University Research Reactor 2318100100012 Institute - Linear Accelerator (KURRI-LINAC) 2318100100013 METHOD (TOF) Capture cross section measurements were carried 2318100100014 out by TOF method. 2318100100015 The neutron flight length from the Ta target to the 2318100100016 sample was 12.10 +- 0.02 m. 2318100100017 (PHWT) Pulse-height weighting technique was applied 2318100100018 to observed gamma-ray spectra to determine the 2318100100019 capture yields. 2318100100020 DETECTOR (SCIN) Pair of C6D6 liquid scintillators for capture 2318100100021 gamma-ray measurement. 2318100100022 INC-SOURCE (PHOTO) A photo-neutron target of Ta was used as a 2318100100023 pulsed neutron source for the neutron TOF measurement. 2318100100024 The target was set at the center of an octagonal 2318100100025 water tank (30 cm in diameter and 10 cm in depth) 2318100100026 as a neutron moderator. The accelerator was operated 2318100100027 in two different conditions 2318100100028 High Energy Low Energy 2318100100029 measurement measurement 2318100100030 above 2 eV below 2 eV 2318100100031 Repetition rate 200 Hz 50 Hz 2318100100032 Pulse width 100 nsec 100 nsec 2318100100033 Average current 63.0 A 16.5 A 2318100100034 Cd filter On Off 2318100100035 HISTORY (20120106C) M.M. 2318100100036 (20180908A) VS. Entry recompile from to main reference.2318100100037 Subents 004-007 added. 2318100100038 STATUS (APRVD) Approved by J.Lee 9 November 2018 2318100100039 ENDBIB 37 0 2318100100040 NOCOMMON 0 0 2318100100041 ENDSUBENT 40 0 2318100199999 SUBENT 23181002 20180909 22712318100200001 BIB 7 41 2318100200002 REACTION (63-EU-151(N,G)63-EU-152,,SIG,,AV) 2318100200003 MONITOR (5-B-10(N,A)3-LI-7,,RYL) The neutron flux is determined2318100200004 by 10B(n,ag) and (n,tot) cross sections from JENDL-4.0.2318100200005 10B sample characteristics: 2318100200006 Chemical Form 10B Metal powder 2318100200007 Isotope Composition 10B: 96.98% 2318100200008 11B: 3.02% 2318100200009 Weight (g) 3.60 2318100200010 Thickness (atoms/kb) 55.305 2318100200011 Size of sample 2.2 cm in diam. 2318100200012 SAMPLE Chemical Form Oxide(Eu2O3) 2318100200013 Isotope Composition 151Eu 97.60(+-0.2)% 2318100200014 153Eu 2.4(+-0.2)% 2318100200015 Weight (g) 0.115(+-0.001) 2318100200016 Thickness (atoms/kb) 0.0966 2318100200017 Size of sample 2.0x2.0 (+-0.02) cm2 2318100200018 (63-EU-151,ENR=0.976) 2318100200019 (63-EU-153,ENR=0.024) 2318100200020 CORRECTION - Correction for the neutron self-shielding and 2318100200021 multiple scattering 2318100200022 - Correction for the capture yield due to the isotopic 2318100200023 impurity in the sample was done by using the present 2318100200024 results of 153Eu (Subent 002) 2318100200025 MISC-COL (MISC) Average neutron energy 2318100200026 STATUS (TABLE) Table 9 of J Nucl Sci Technol. 54(2017)1046 2318100200027 ERR-ANALYS (ERR-T) The total uncertainties determined from the 2318100200028 following partial uncertainties: 2318100200029 (ERR-1) Weighting function 3.2% 2318100200030 (ERR-2,0.8,1.2) Correction of neutron multiple- 2318100200031 scattering and self-shielding 2318100200032 (ERR-3,0.1,3.0) Correction of impurity in the sample 2318100200033 (ERR-4,0.2,1.5) Sample thickness 2318100200034 (ERR-5,0.1,0.2) 10B(n,a) cross section 2318100200035 (ERR-S,3.,48.) Statistical 2318100200036 Energy range (eV) Statistical error (%) 2318100200037 0.005-0.02 5-23 2318100200038 0.02-1 3-13 2318100200039 1-10 3-13 2318100200040 10-100 5-9 2318100200041 100-2600 6-14 2318100200042 2600-25000 20-48 2318100200043 ENDBIB 41 0 2318100200044 COMMON 1 3 2318100200045 ERR-1 2318100200046 PER-CENT 2318100200047 3.2 2318100200048 ENDCOMMON 3 0 2318100200049 DATA 5 51 2318100200050 EN-MIN EN-MAX DATA ERR-T MISC 2318100200051 EV EV B B EV 2318100200052 5.00E-03 6.42E-03 2.53E+04 7.12E+03 5.64E-03 2318100200053 6.42E-03 8.24E-03 1.88E+04 3.37E+03 7.25E-03 2318100200054 8.24E-03 1.06E-02 1.86E+04 2.66E+03 9.30E-03 2318100200055 1.06E-02 1.36E-02 1.50E+04 1.68E+03 1.19E-02 2318100200056 1.36E-02 1.75E-02 1.34E+04 1.27E+03 1.53E-02 2318100200057 1.75E-02 2.24E-02 1.10E+04 9.08E+02 1.97E-02 2318100200058 2.24E-02 2.88E-02 9.05E+03 6.83E+02 2.53E-02 2318100200059 2.88E-02 3.70E-02 6.71E+03 4.63E+02 3.25E-02 2318100200060 3.70E-02 4.74E-02 5.22E+03 3.50E+02 4.17E-02 2318100200061 4.74E-02 6.09E-02 4.09E+03 2.70E+02 5.36E-02 2318100200062 6.09E-02 7.82E-02 2.92E+03 1.94E+02 6.88E-02 2318100200063 7.82E-02 1.00E-01 2.22E+03 1.56E+02 8.83E-02 2318100200064 1.00E-01 1.29E-01 1.79E+03 1.35E+02 1.13E-01 2318100200065 1.29E-01 1.66E-01 1.65E+03 1.40E+02 1.46E-01 2318100200066 1.66E-01 2.13E-01 1.65E+03 1.59E+02 1.87E-01 2318100200067 2.13E-01 2.73E-01 2.50E+03 2.77E+02 2.40E-01 2318100200068 2.73E-01 3.51E-01 5.07E+03 4.79E+02 3.08E-01 2318100200069 3.51E-01 4.50E-01 1.06E+03 9.55E+02 3.96E-01 2318100200070 4.50E-01 5.78E-01 1.19E+03 1.32E+03 5.08E-01 2318100200071 5.78E-01 7.42E-01 1.33E+03 1.54E+02 6.52E-01 2318100200072 7.42E-01 9.53E-01 5.09E+03 1.09E+02 8.38E-01 2318100200073 9.53E-01 1.22E+00 1.50E+03 1.91E+02 1.08E+00 2318100200074 1.22E+00 1.57E+00 2.37E+03 3.13E+01 1.38E+00 2318100200075 1.57E+00 2.02E+00 2.14E+03 2.75E+01 1.77E+00 2318100200076 2.02E+00 2.59E+00 1.36E+03 1.99E+01 2.28E+00 2318100200077 2.59E+00 3.33E+00 6.15E+03 4.73E+01 2.92E+00 2318100200078 3.33E+00 4.27E+00 1.25E+03 8.09E+01 3.75E+00 2318100200079 4.27E+00 5.48E+00 1.64E+02 2.29E+01 4.82E+00 2318100200080 5.48E+00 7.04E+00 1.67E+02 2.17E+01 6.19E+00 2318100200081 7.04E+00 9.04E+00 6.84E+02 4.88E+01 7.95E+00 2318100200082 9.04E+00 1.16E+01 2.70E+02 2.60E+01 1.02E+01 2318100200083 1.16E+01 1.49E+01 2.80E+02 2.59E+01 1.31E+01 2318100200084 1.49E+01 1.91E+01 2.24E+02 2.24E+01 1.68E+01 2318100200085 1.91E+01 2.46E+01 2.47E+02 2.30E+01 2.16E+01 2318100200086 2.46E+01 3.16E+01 2.85E+02 2.46E+01 2.77E+01 2318100200087 3.16E+01 4.05E+01 1.88E+02 1.90E+01 3.56E+01 2318100200088 4.05E+01 5.20E+01 2.93E+02 2.41E+01 4.57E+01 2318100200089 5.20E+01 6.68E+01 1.44E+02 1.57E+01 5.87E+01 2318100200090 6.68E+01 8.58E+01 1.41E+02 1.53E+01 7.54E+01 2318100200091 8.58E+01 1.10E+02 1.36E+02 1.49E+01 9.68E+01 2318100200092 1.10E+02 1.65E+02 1.17E+02 1.16E+01 1.33E+02 2318100200093 1.65E+02 2.72E+02 9.69E+01 9.45E+00 2.08E+02 2318100200094 2.72E+02 4.48E+02 6.82E+01 7.57E+00 3.44E+02 2318100200095 4.48E+02 7.39E+02 5.19E+01 6.30E+00 5.67E+02 2318100200096 7.39E+02 1.22E+03 3.49E+01 5.17E+00 9.34E+02 2318100200097 1.22E+03 2.01E+03 2.62E+01 4.51E+00 1.54E+03 2318100200098 2.01E+03 3.31E+03 1.87E+01 3.50E+00 2.54E+03 2318100200099 3.31E+03 5.46E+03 1.39E+01 3.35E+00 4.19E+03 2318100200100 5.46E+03 9.00E+03 8.68E+00 3.08E+00 6.90E+03 2318100200101 9.00E+03 1.48E+04 6.19E+01 2.73E+00 1.14E+04 2318100200102 1.48E+04 2.45E+04 4.84E+01 2.56E+00 1.88E+04 2318100200103 ENDDATA 53 0 2318100200104 ENDSUBENT 103 0 2318100299999 SUBENT 23181003 20180909 22712318100300001 BIB 6 39 2318100300002 REACTION (63-EU-153(N,G)63-EU-154,,SIG,,AV) 2318100300003 SAMPLE Chemical Form Oxide(Eu2O3) 2318100300004 Isotope Composition 153Eu 99.71(+-0.06)% 2318100300005 151Eu 0.29 (+-0.006)% 2318100300006 Weight (g) 0.114 (+-0.001) 2318100300007 Thickness (atoms/kb) 0.0968 2318100300008 Size of sample 2.0x2.0 (+-0.02) cm2 2318100300009 (63-EU-153,ENR=0.9971) 2318100300010 (63-EU-151,ENR=0.0029) 2318100300011 MONITOR (5-B-10(N,A)3-LI-7,,RYL) The neutron flux is determined2318100300012 by 10B(n,ag) and (n,tot) cross sections from JENDL-4.0.2318100300013 10B sample characteristics: 2318100300014 Chemical Form 10B Metal powder 2318100300015 Isotope Composition 10B: 96.98% 2318100300016 11B: 3.02% 2318100300017 Weight (g) 3.60 2318100300018 Thickness (atoms/kb) 55.305 2318100300019 Size of sample 2.2 cm in diam. 2318100300020 CORRECTION - Correction for the neutron self-shielding and 2318100300021 multiple scattering by MCNP-4C calculations with 2318100300022 nuclear data taken from JENDL-4.0. 2318100300023 - Correction for the capture yields due to the 2318100300024 isotopic impurity in the sample was done by using 2318100300025 the present results of 151Eu (Subent 002). 2318100300026 ERR-ANALYS (ERR-T) The total uncertainties determined from the 2318100300027 following partial uncertainties: 2318100300028 (ERR-1) Weighting function 3.2% 2318100300029 (ERR-2,0.5,1.0) Correction of neutron multiple- 2318100300030 scattering and self-shielding 2318100300031 (ERR-3,0.1,9.0) Correction of impurity in the sample 2318100300032 (ERR-4,0.9,1.2) Sample thickness 2318100300033 (ERR-5,0.1,0.2) 10B(n,a) cross section 2318100300034 (ERR-S,3.,73.) Statistical errors 2318100300035 Energy range (eV) Statistical error (%) 2318100300036 0.02-1 3-56 2318100300037 1-10 3-73 2318100300038 10-100 5-7 2318100300039 100-2600 6-23 2318100300040 STATUS (TABLE) Table 10 of J Nucl Sci Technol. 54(2017)1046. 2318100300041 ENDBIB 39 0 2318100300042 COMMON 1 3 2318100300043 ERR-1 2318100300044 PER-CENT 2318100300045 3.2 2318100300046 ENDCOMMON 3 0 2318100300047 DATA 5 22 2318100300048 EN-MIN EN-MAX DATA ERR-T MISC 2318100300049 EV EV B B EV 2318100300050 2.88E-02 3.70E-02 3.11E+02 3.83E+01 3.25E-02 2318100300051 3.70E-02 6.09E-02 2.60E+02 2.86E+01 4.67E-02 2318100300052 6.09E-02 1.00E-01 1.97E+02 2.37E+01 7.70E-02 2318100300053 1.00E-01 2.13E-01 1.35E+02 2.40E+01 1.41E-01 2318100300054 2.13E-01 3.51E-01 9.15E+01 4.04E+01 2.69E-01 2318100300055 3.51E-01 5.78E-01 7.11E+01 2.93E+01 4.43E-01 2318100300056 5.78E-01 9.53E-01 6.76E+01 4.16E+01 7.31E-01 2318100300057 9.53E-01 1.57E+00 5.06E+01 4.18E+01 1.20E+00 2318100300058 1.57E+00 2.02E+00 2.15E+02 6.38E+01 1.77E+00 2318100300059 2.02E+00 2.59E+00 1.48E+03 9.86E+01 2.28E+00 2318100300060 2.59E+00 3.33E+00 6.21E+02 4.72E+01 2.92E+00 2318100300061 3.33E+00 4.27E+00 7.80E+02 5.44E+01 3.75E+00 2318100300062 4.27E+00 7.04E+00 1.41E+02 1.61E+01 5.40E+00 2318100300063 7.04E+00 1.16E+01 2.09E+02 1.88E+01 8.90E+00 2318100300064 1.16E+01 1.91E+01 2.18E+02 1.83E+01 1.47E+01 2318100300065 1.91E+01 3.16E+01 1.84E+02 1.58E+01 2.42E+01 2318100300066 3.16E+01 5.20E+01 1.33E+02 1.47E+01 3.99E+01 2318100300067 5.20E+01 8.58E+01 1.41E+02 1.43E+01 6.58E+01 2318100300068 8.58E+01 1.65E+02 8.38E+01 9.93E+00 1.16E+02 2318100300069 1.65E+02 4.48E+02 4.85E+01 6.24E+00 2.56E+02 2318100300070 4.48E+02 1.22E+03 2.35E+01 4.54E+00 6.95E+02 2318100300071 1.22E+03 3.31E+03 1.20E+01 3.30E+00 1.89E+03 2318100300072 ENDDATA 24 0 2318100300073 ENDSUBENT 72 0 2318100399999 SUBENT 23181004 20180909 22712318100400001 BIB 3 21 2318100400002 REACTION (63-EU-151(N,G)63-EU-152,,SIG,,,DERIV) 2318100400003 ERR-ANALYS (ERR-T) The total uncertainties determined from the 2318100400004 following partial uncertainties: 2318100400005 (ERR-1) Weighting function 3.2% 2318100400006 (ERR-2,0.8,1.2) Correction of neutron multiple- 2318100400007 scattering and self-shielding 2318100400008 (ERR-3,0.1,3.0) Correction of impurity in the sample 2318100400009 (ERR-4,0.2,1.5) Sample thickness 2318100400010 (ERR-5,0.1,0.2) 10B(n,a) cross section 2318100400011 (ERR-S,3.,48.) Statistical errors of the net TOF 2318100400012 spectrum and PH spectrum 2318100400013 Energy range (eV) Statistical error (%) 2318100400014 0.005-0.02 5-23 2318100400015 0.02-1 3-13 2318100400016 1-10 3-13 2318100400017 10-100 5-9 2318100400018 100-2600 6-14 2318100400019 2600-25000 20-48 2318100400020 STATUS (TABLE) Table 8 of J Nucl Sci Technol. 54(2017)1046. 2318100400021 (DEP,23181002) Average cross section for the incident 2318100400022 neutron energy interval 0.0224 - 0.0288 eV. 2318100400023 ENDBIB 21 0 2318100400024 COMMON 1 3 2318100400025 ERR-1 2318100400026 PER-CENT 2318100400027 3.2 2318100400028 ENDCOMMON 3 0 2318100400029 DATA 3 1 2318100400030 EN DATA ERR-T 2318100400031 EV B B 2318100400032 0.0253 9051. 683. 2318100400033 ENDDATA 3 0 2318100400034 ENDSUBENT 33 0 2318100499999 SUBENT 23181005 20180909 22712318100500001 BIB 4 5 2318100500002 REACTION (63-EU-153(N,G)63-EU-154,,SIG,,,DERIV) 2318100500003 ANALYSIS Thermal cross section determined by extrapolation. 2318100500004 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties. 2318100500005 STATUS (TABLE) Table 8 of J Nucl Sci Technol. 54(2017) 1046. 2318100500006 (DEP,23181003) 2318100500007 ENDBIB 5 0 2318100500008 NOCOMMON 0 0 2318100500009 DATA 3 1 2318100500010 EN DATA DATA-ERR 2318100500011 EV B B 2318100500012 0.0253 364. 44. 2318100500013 ENDDATA 3 0 2318100500014 ENDSUBENT 13 0 2318100599999 SUBENT 23181006 20180909 22712318100600001 BIB 3 4 2318100600002 REACTION (63-EU-151(N,G)63-EU-152,,RI,,,DERIV) 2318100600003 STATUS (TABLE) Table 8 of J Nucl Sci Technol. 54(2017) 1046. 2318100600004 (DEP,23181002) 2318100600005 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties. 2318100600006 ENDBIB 4 0 2318100600007 NOCOMMON 0 0 2318100600008 DATA 4 1 2318100600009 EN-MIN EN-MAX DATA DATA-ERR 2318100600010 EV MEV B B 2318100600011 0.5 10. 3490. 162. 2318100600012 ENDDATA 3 0 2318100600013 ENDSUBENT 12 0 2318100699999 SUBENT 23181007 20180909 22712318100700001 BIB 3 4 2318100700002 REACTION (63-EU-153(N,G)63-EU-154,,RI,,,DERIV) 2318100700003 STATUS (TABLE) Table 8 of J Nucl Sci Technol. 54(2017) 1046. 2318100700004 (DEP,23181003) 2318100700005 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties. 2318100700006 ENDBIB 4 0 2318100700007 NOCOMMON 0 0 2318100700008 DATA 4 1 2318100700009 EN-MIN EN-MAX DATA DATA-ERR 2318100700010 EV MEV B B 2318100700011 0.5 10. 1538. 106. 2318100700012 ENDDATA 3 0 2318100700013 ENDSUBENT 12 0 2318100799999 ENDENTRY 7 0 2318199999999