ENTRY 32738 20170509 31793273800000001 SUBENT 32738001 20170509 31793273800100001 BIB 16 53 3273800100002 TITLE Ground-state and isomeric-state cross sections for 3273800100003 the 138Ce(n,2n)137Ce reaction from its threshold to 3273800100004 20 MeV 3273800100005 AUTHOR (Junhua Luo, Li An, Li Jiang) 3273800100006 INSTITUTE (3CPRHXU,3CPRNPC) 3273800100007 REFERENCE (J,RCA,103,613,2015) 3273800100008 #doi:10.1515/ract-2015-2402 3273800100009 FACILITY (NGEN,3CPRNPC) PD-300 neutron generator 3273800100010 SAMPLE Three pellets, about 0.2 cm in thickness and 20 mm in 3273800100011 diameter, were formed by pressing approximately 10 3273800100012 gram of CeO2 (99.99% pure) powder at 980 Mpa. The 3273800100013 samples were irradiated in contact with the target 3273800100014 and sandwiched between two standard Nb foils (99.99% 3273800100015 pure, 0.5 mm thick) of the same diameter. 3273800100016 INC-SOURCE (D-T) Neutrons were produced by the T(d,n)4He 3273800100017 reaction with an effective deuteron beam energy of 3273800100018 125 keV and beam current of 200 uA. 3273800100019 DETECTOR (HPGE) A high-purity germanium detector, crystal 3273800100020 diameter: 70.1 mm, crystal length: 72.3 mm, with a 3273800100021 relative efficiency of about 68% and an energy 3273800100022 resolution of 1.69 keV at 1.332 keV for 60Co. The 3273800100023 detector was pre-calibrated for energy and efficiency 3273800100024 by using the standard gamma ray sources 54Mn, 57Co, 3273800100025 60Co, 109Cd, 133Ba, 137Cs, 152Eu, 241Am and 226Ra. 3273800100026 (FISCH) The neutron flux was monitored by a uranium 3273800100027 fission chamber allowing corrections to be made for 3273800100028 small variations in the yield. 3273800100029 METHOD (ACTIV) Irradiation of the samples was lasted 3273800100030 approximately 2 hours with a yield about 3 to 3273800100031 4E10 n/(4pi*s). The groups of samples were placed at 3273800100032 0, 90, and 135 degree relative to the beam direction 3273800100033 and centered about a 2.40 mg/cm2 thick T-Ti target at 3273800100034 a distance of about 5 cm. 3273800100035 MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) 3273800100036 DECAY-MON (41-NB-92-M,10.15D,DG,934.43,0.9907) 3273800100037 MONIT-REF (,M.Wagner+,B,PH-DAT,13-5,1990) The cross section of 3273800100038 monitor reaction was taken from the reference. 3273800100039 CORRECTION Corrections were made for the self-absorption of 3273800100040 the sample at a given gamma-ray energy and the 3273800100041 counting geometry. 3273800100042 ERR-ANALYS (ERR-T) Total uncertainty 3273800100043 (ERR-S,1.8,11.0) Counting statistics 1.8-11.0% 3273800100044 (ERR-1) Isotopic abundance 4.0% 3273800100045 (ERR-2,2.0,3.0) Detector efficiency 2.0-3.0% 3273800100046 (ERR-3) Weight of samples 0.1% 3273800100047 (ERR-4) Self-absorption of gamma-ray about 0.5% 3273800100048 (ERR-5) Relative gamma-ray intensity about 1.0% 3273800100049 (ERR-6,0.09,0.4) Half-life 0.09-0.4% 3273800100050 (ERR-7,0.1,0.5) Uncertainties of irradiation, cooling 3273800100051 and measuring times 0.1-0.5% 3273800100052 STATUS (TABLE) Data were obtained from TABLE 4 of Radiochim. 3273800100053 Acta, 103(9), 613, 2015. 3273800100054 HISTORY (20170509C) Compiled by Xi Tao (CNDC) 3273800100055 ENDBIB 53 0 3273800100056 COMMON 4 3 3273800100057 ERR-1 ERR-3 ERR-4 ERR-5 3273800100058 PER-CENT PER-CENT PER-CENT PER-CENT 3273800100059 4.0 0.1 0.5 1.0 3273800100060 ENDCOMMON 3 0 3273800100061 ENDSUBENT 60 0 3273800199999 SUBENT 32738002 20170509 31793273800200001 BIB 3 6 3273800200002 REACTION 1(58-CE-138(N,2N)58-CE-137-M,,SIG) 3273800200003 2(58-CE-138(N,2N)58-CE-137-G,,SIG) 3273800200004 3(58-CE-138(N,2N)58-CE-137,,SIG) 3273800200005 DECAY-DATA1(58-CE-137-M,34.80HR,DG,254.29,0.111) 3273800200006 2(58-CE-137-G,9.11HR,DG,447.15,0.0169) 3273800200007 SAMPLE (58-CE-138,NAT=0.0025) 3273800200008 ENDBIB 6 0 3273800200009 NOCOMMON 0 0 3273800200010 DATA 10 3 3273800200011 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 23273800200012 DATA 3ERR-T 3MONIT MONIT-ERR 3273800200013 MEV MEV MB MB MB MB 3273800200014 MB MB MB MB 3273800200015 13.5 0.2 795. 62. 546. 66.3273800200016 1341. 128. 457.9 6.8 3273800200017 14.1 0.2 930. 59. 564. 51.3273800200018 1494. 110. 459.8 6.8 3273800200019 14.8 0.2 1008. 44. 604. 84.3273800200020 1612. 128. 459.7 5.0 3273800200021 ENDDATA 10 0 3273800200022 ENDSUBENT 21 0 3273800299999 ENDENTRY 2 0 3273899999999