ENTRY 33085 20160617 31753308500000001 SUBENT 33085001 20160617 31753308500100001 BIB 17 50 3308500100002 TITLE 151Eu(n,g)152m1Eu reaction cross-section measurement 3308500100003 at the neutron energies of 1.12,2.12,3.12 and 4.12 MeV 3308500100004 AUTHOR (S.Badwar, R.Ghosh, B.M.Lawriniang, V.Vansola, 3308500100005 A.Gopalakrishna, H.Naik, Y.Naik, S.V.Suryanarayana, 3308500100006 S.Y.Salunkhe, A.Agarwal, S.Ware, A.K.Gupta, B.Jyrwa, 3308500100007 S.Ganesan, P.Singh, A.Goswami) 3308500100008 INSTITUTE (3INDBDA,3INDTRM) 3308500100009 (3INDIND) North Eastern Hill University, Shillong, 3308500100010 Meghalaya 3308500100011 (3INDIND) Radiation Medicine Centre, Mumbai 3308500100012 REFERENCE (J,JRN,307,1385,2016) 3308500100013 FACILITY (VDGT,3INDTRM) Folded Tandem Ion Accelerator 3308500100014 (VDGT,3INDTRM) 14UD Pelletron accelerator 3308500100015 SAMPLE (63-EU-151,NAT=0.478) 3308500100016 Anhydrous europium oxide powder with purity ~99.99% 3308500100017 wrapped with 0.025 mm thick aluminium foil. 3308500100018 INC-SOURCE (P-LI7) For proton energy of 3-4 MeV, circular LiF 3308500100019 pallet of 1 cm diameter and 3 mm thickness was used. 3308500100020 For proton energy of 5-6 MeV, the lithium foil used 3308500100021 was made up of natural lithium with thickness of 3.7 3308500100022 mg/cm2, sandwiched between two tantalum foils. 3308500100023 DETECTOR (HPGE) Pre-calibrated 80 cm3 HPGe detector coupled to 3308500100024 a PC based 4096 channel analyzer. 3308500100025 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 3308500100026 DECAY-MON (79-AU-198-G,2.6948D,DG,411.80205,0.9562) 3308500100027 MONIT-REF 1(,M.B.Chadwick+,3,ENDF/B-VII.1,,2006) 3308500100028 2(,K.Shibata+,3,JENDL-4.0,,2011) 3308500100029 FLAG (1.) Folded Tandem Ion Accelerator 3308500100030 (2.) 14UD Pelletron Accelerator 3308500100031 METHOD (GSPEC) 3308500100032 (ACTIV) Irradiated for 5.6 to 13.4 hr. 3308500100033 ADD-RES The cross section of 151Eu(n,g)152m1Eu at neutron 3308500100034 energies of 1.12 and 2.12 MeV obtained by using gold 3308500100035 monitor cross sections taken from J,JNE/AB 3308500100036 18(1964)491, and J,AKE 26(1975)80 was also reported. 3308500100037 (COMP) The reaction cross section was also calculated 3308500100038 theoretically by using computer code TALYS 1.6. 3308500100039 ERR-ANALYS (ERR-T) Combined uncertainties from both statistical 3308500100040 and systematic errors 3308500100041 (ERR-S,3.21,3.26) Counting statistics 3308500100042 (ERR-SYS,11.18,11.31) The systematic error is due to 3308500100043 following uncertainties: 3308500100044 (ERR-1) Irradiation time ~ 0.1% 3308500100045 (ERR-2) Half-life of the reaction product and the 3308500100046 gamma-ray abundance ~ 11% 3308500100047 (ERR-3) Detector efficiency ~ 3% 3308500100048 (MONIT-ERR,1.,2.) 3308500100049 HISTORY (20160617C) Compiled by S.Badwar,B.Jyrwa,NEHU, 3308500100050 Shillong, Meghalaya, India 3308500100051 STATUS (TABLE) Table 2 of J.Rad.Nucl.Chem. 307(2016)1385 3308500100052 ENDBIB 50 0 3308500100053 COMMON 3 3 3308500100054 ERR-1 ERR-2 ERR-3 3308500100055 PER-CENT PER-CENT PER-CENT 3308500100056 0.1 11. 3. 3308500100057 ENDCOMMON 3 0 3308500100058 ENDSUBENT 57 0 3308500199999 SUBENT 33085002 20160617 31753308500200001 BIB 3 6 3308500200002 REACTION 1(63-EU-151(N,G)63-EU-152-M1,,SIG) 3308500200003 Normalized by ENDF-B/VII.1 3308500200004 2(63-EU-151(N,G)63-EU-152-M1,,SIG) 3308500200005 Normalized by JENDL-4.0 3308500200006 DECAY-DATA (63-EU-152-M1,9.3116HR,DG,841.63,0.142) 3308500200007 STATUS (TABLE) Table 2 of J.Radioanal.Nucl.Chem.307(2016)1385 3308500200008 ENDBIB 6 0 3308500200009 NOCOMMON 0 0 3308500200010 DATA 9 4 3308500200011 EN EN-RSL DATA 1ERR-T 1MONIT 1DATA 23308500200012 ERR-T 2MONIT 2FLAG 3308500200013 MEV MEV MB MB MB MB 3308500200014 MB MB NO-DIM 3308500200015 1.12 0.11 123.54 5.93 77.552 124.63 3308500200016 5.98 78.234 1. 3308500200017 2.12 0.15 56.04 2.74 47.347 60.02 3308500200018 2.94 50.712 1. 3308500200019 3.12 0.21 29.36 1.41 22.712 23.99 3308500200020 1.18 18.558 2. 3308500200021 4.12 0.22 13.46 1.82 11.490 13.62 3308500200022 1.85 11.637 2. 3308500200023 ENDDATA 12 0 3308500200024 ENDSUBENT 23 0 3308500299999 ENDENTRY 2 0 3308599999999