ENTRY 32753 20171010 31813275300000001 SUBENT 32753001 20171010 31813275300100001 BIB 16 52 3275300100002 TITLE Activation cross section and isomeric cross-section 3275300100003 ratio for the 151Eu(n,a)148m,gPm process from 3275300100004 threshold up to 20 MeV 3275300100005 AUTHOR (Junhua Luo, Long He) 3275300100006 INSTITUTE (3CPRHXU) 3275300100007 REFERENCE (J,JRN,311,349,2017) 3275300100008 #doi:10.1007/s10967-016-5023-y 3275300100009 FACILITY (NGEN,3CPRNPC) PD-300 Neutron Generator 3275300100010 SAMPLE Three pellets, about 0.15 cm thick and 20 mm in 3275300100011 diameter were formed by pressing approximately 10 3275300100012 gram of Eu2O3 (99.99% pure) powder (natural isotopic 3275300100013 composition) at 980 MPa to form a pellet. The samples 3275300100014 were irradiated in contact with the target and 3275300100015 sandwiched between two standard Al foils (99.999% 3275300100016 pure, 0.3 mm thick) of the same diameter used to 3275300100017 monitor the neutron fluence via the 27Al(n,a)24Na 3275300100018 reaction. 3275300100019 INC-SOURCE (D-T) A 2.40 mg/cm2 thick tritium-titanium (T-Ti) 3275300100020 target at a distance of about 5 cm. Neutrons were 3275300100021 produced with an effective deuteron beam energy of 3275300100022 125 keV and beam current of 200 uA. 3275300100023 DETECTOR (HPGE) A high-purity germanium detector (ORTEC, model 3275300100024 GEM 60P, crystal diameter: 70.1 mm, crystal length: 3275300100025 72.3 mm) with a relative efficiency of about 68% and 3275300100026 an energy resolution of 1.69 keV at 1.332 MeV for 3275300100027 60Co. The efficiency of the detector was 3275300100028 pre-calibrated using the standard gamma sources 54Mn, 3275300100029 57Co, 60Co, 109Cd, 133Ba, 137Cs, 152Eu, 241Am and 3275300100030 226Ra. 3275300100031 METHOD (ACTIV) Irradiation of the samples was lasted 3275300100032 approximately 2 hours with a yield about 3-4E10 3275300100033 n/(4pi*s). The groups of samples were placed at 0, 90 3275300100034 and 135 degree relative to the beam direction. 3275300100035 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3275300100036 DECAY-MON (11-NA-24,14.997HR,DG,1368.6,1.00) 3275300100037 MONIT-REF (,M.Wagner+,B,PH-DAT,13-5,1990) 3275300100038 CORRECTION Corrections were made for the self-absorption of the 3275300100039 sample at 629.97 and 1465.12 keV gamma-rays. 3275300100040 ERR-ANALYS (ERR-T) Total uncertainty lies between 6.7- 33.3% 3275300100041 (ERR-S,1.6,33.0) Counting statistics 1.6-33.0% 3275300100042 (MONIT-ERR) Standard cross sections 0.5-0.7% 3275300100043 (ERR-1) Isotopic abundance 0.1% 3275300100044 (ERR-2,2.0,3.0) Detector efficiency 2.0-3.0% 3275300100045 (ERR-3) Weight of samples 0.1% 3275300100046 (ERR-4) Self-absorption of gamma-ray about 0.5% 3275300100047 (ERR-5,1.0,2.3) Relative gamma-ray intensity 1.0-2.3% 3275300100048 (ERR-6,0.04,0.3) Half-life 0.04-0.3% 3275300100049 (ERR-7) Uncertainties of irradiation, cooling and 3275300100050 measuring times about 0.1% 3275300100051 STATUS (TABLE) Data were obtained from TABLE 4 of 3275300100052 J.Radioanal.Nucl.Chem.,311,349,2017. 3275300100053 HISTORY (20171010C) Compiled by Xi Tao (CNDC) 3275300100054 ENDBIB 52 0 3275300100055 COMMON 4 3 3275300100056 ERR-1 ERR-3 ERR-4 ERR-7 3275300100057 PER-CENT PER-CENT PER-CENT PER-CENT 3275300100058 0.1 0.1 0.5 0.1 3275300100059 ENDCOMMON 3 0 3275300100060 ENDSUBENT 59 0 3275300199999 SUBENT 32753002 20171010 31813275300200001 BIB 4 8 3275300200002 REACTION 1(63-EU-151(N,A)61-PM-148-M,,SIG) 3275300200003 2(63-EU-151(N,A)61-PM-148-G,,SIG) 3275300200004 3(63-EU-151(N,A)61-PM-148,,SIG) 3275300200005 DECAY-DATA1(61-PM-148-M,41.29D,DG,629.97,0.890) 3275300200006 2(61-PM-148-G,5.368D,DG,1465.12,0.222) 3275300200007 SAMPLE (63-EU-151,NAT=0.4781) 3275300200008 CORRECTION2Contribution of 151Eu(n,a)148mPm isomeric trandition 3275300200009 is subtracted. 3275300200010 ENDBIB 8 0 3275300200011 NOCOMMON 0 0 3275300200012 DATA 10 3 3275300200013 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 23275300200014 DATA 3ERR-T 3MONIT MONIT-ERR 3275300200015 MEV MEV MB MB MB MB 3275300200016 MB MB MB MB 3275300200017 13.5 0.2 1.5 0.3 1.2 0.23275300200018 2.7 0.5 125.7 0.8 3275300200019 14.1 0.2 1.8 0.6 1.4 0.23275300200020 3.2 0.8 121.6 0.6 3275300200021 14.8 0.2 2.3 0.6 1.5 0.13275300200022 3.8 0.7 111.9 0.5 3275300200023 ENDDATA 10 0 3275300200024 ENDSUBENT 23 0 3275300299999 ENDENTRY 2 0 3275399999999