ENTRY 32703 20120907 31573270300000001 SUBENT 32703001 20120907 31573270300100001 BIB 15 49 3270300100002 TITLE Cross section measurements for 141Pr(n,g)142Pr reaction3270300100003 at neutron energies from 13.5 to 14.8 MeV 3270300100004 AUTHOR (Junhua Luo,Jiuning Han,Rong Liu,Li Jiang) 3270300100005 INSTITUTE (3CPRHXU) School of Physics and Electromechanical 3270300100006 Engineering 3270300100007 (3CPRNPC) 3270300100008 REFERENCE (J,JRN,293,261,2012) 3270300100009 #doi:10.1007/s10967-012-1778-y 3270300100010 FACILITY (NGEN,3CPRNPC) PD-300 neutron generator 3270300100011 SAMPLE About 9 g of Pr2O3 powder of natural isotopic 3270300100012 composition (>99.99% pure) was pressed at 10 ton/cm2, 3270300100013 and a pellet, 0.3 cm thick and 2.0 cm in diameter was 3270300100014 obtained. 3270300100015 DETECTOR (HPGE) The crystal geometry is 70.1 x 72.3 mm in 3270300100016 diameter and length. The relative efficiency is about 3270300100017 68%, and energy resolution is 1.69 keV at 1332 keV 3270300100018 gamma ray from Co-60. 3270300100019 METHOD (ACTIV) Irradiation of the samples was carried out and 3270300100020 lasted 121 min with a yield around 3E10 to 4E10 3270300100021 n/(4pi*s). 3270300100022 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3270300100023 DECAY-MON (11-NA-24,14.959HR,DG,1368.6,1.00) 3270300100024 MONIT-REF (,M.Wagner+,B,PH-DAT,13-5,1990) 3270300100025 The cross section of monitor reaction was determined by3270300100026 interpolation of the evaluated values of the reference.3270300100027 INC-SOURCE (D-T) The tritium-titanium (T-Ti) target was used in 3270300100028 the generator. The effective source neutron energy at 3270300100029 irradiation position was determined by the Nb/Zr 3270300100030 method. 3270300100031 ERR-ANALYS (ERR-T) Total uncertainty were due to the counting 3270300100032 statistics, standard cross sections, detector 3270300100033 efficiency, weight of samples, self-absorption of 3270300100034 gamma-ray and the coincidence sum effect of cascade 3270300100035 gamma-rays, the uncertainties of irradiation, cooling 3270300100036 and measuring times, isotopic abundance, etc. 3270300100037 (ERR-S,0.9,8.) Counting statistics 3270300100038 (ERR-1,0.1,1.) Uncertainties of irradiation, cooling 3270300100039 and measuring times 3270300100040 (ERR-2) Isotopic abundance (0.1%) 3270300100041 (ERR-3) Detector efficiency (3.%) 3270300100042 (ERR-4) Weight of sample (0.1%) 3270300100043 (ERR-5) Self-absorption of gamma-ray (around 0.5%) 3270300100044 (ERR-6,0.,5.) Coincidence sum effect of cascade 3270300100045 gamma-rays 3270300100046 (MONIT-ERR) Standard cross sections uncertainty 3270300100047 STATUS (TABLE) All measured reactions data and monitor 3270300100048 reaction data are taken from Table3 at page 263 in 3270300100049 J,JRN,293,261,2012. 3270300100050 HISTORY (20120907C)Compiled by Guochang CHEN (CNDC) 3270300100051 ENDBIB 49 0 3270300100052 COMMON 5 3 3270300100053 EN-RSL ERR-2 ERR-3 ERR-4 ERR-5 3270300100054 MEV PER-CENT PER-CENT PER-CENT PER-CENT 3270300100055 0.2 0.1 3.0 0.1 0.5 3270300100056 ENDCOMMON 3 0 3270300100057 ENDSUBENT 56 0 3270300199999 SUBENT 32703002 20120907 31573270300200001 BIB 2 2 3270300200002 REACTION (59-PR-141(N,G)59-PR-142,,SIG) 3270300200003 DECAY-DATA (59-PR-142,19.12HR,DG,1575.85,0.037) 3270300200004 ENDBIB 2 0 3270300200005 NOCOMMON 0 0 3270300200006 DATA 5 3 3270300200007 EN DATA ERR-T MONIT MONIT-ERR 3270300200008 MEV MB MB MB MB 3270300200009 13.5 3.3 0.2 125.7 0.8 3270300200010 14.1 2.7 0.2 121.6 0.6 3270300200011 14.8 2.2 0.2 111.9 0.5 3270300200012 ENDDATA 5 0 3270300200013 ENDSUBENT 12 0 3270300299999 ENDENTRY 2 0 3270399999999