ENTRY 32674 20180419 31843267400000001 SUBENT 32674001 20180419 31843267400100001 BIB 16 54 3267400100002 TITLE Cross-sections for formation of 195mPt through 3267400100003 natPt(n,x)195mPt reaction over neutron energy range 3267400100004 13-15 MeV 3267400100005 AUTHOR (Junhua Luo, Xinxing Wang, Zhenlai Liu, Fei Tuo, 3267400100006 Xiangzhong Kong) 3267400100007 INSTITUTE (3CPRHXU,3CPRLNZ) 3267400100008 REFERENCE (J,RPC,79,1018,2010) 3267400100009 FACILITY (NGEN,3CPRLNZ) ZF-300-II Intense Neutron Generator 3267400100010 INC-SOURCE (D-T) The tritium-titanium (T-Ti) target used in the 3267400100011 generator was 1.35 mg/cm2 thick. 3267400100012 DETECTOR (HPGE) CH8403 coaxial high-purity germanium detector 3267400100013 made in the People Republic of China with a relative 3267400100014 efficiency of 20% and an energy resolution of 3 keV 3267400100015 at 1332 keV. 3267400100016 SAMPLE About 1.5 gram Pt(>99.99% purity) was made into a 3267400100017 pellet (10 mm diameter). Thin Nb(>99.999% purity) or 3267400100018 Al(>99.999% purity) foils were attached in the front 3267400100019 and at the back of each sample as neutron flux 3267400100020 monitor foils. 3267400100021 METHOD (ACTIV) Irradiation lasted 6-10 h with a yield of 3267400100022 around 3E10 to 4E10 n/(4pi.s). 3267400100023 MONITOR ((MONIT1)41-NB-93(N,2N)41-NB-92-M,,SIG) 3267400100024 ((MONIT2)13-AL-27(N,A)11-NA-24,,SIG) 3267400100025 DECAY-MON ((MONIT1)41-NB-92-M,10.15D,DG,934.4,0.9907) 3267400100026 ((MONIT2)11-NA-24,14.959HR,DG,1368.6,1.00) 3267400100027 MONIT-REF (,M.Wagner+,B,PH-DAT,13-5,,1990) 3267400100028 The cross sections of monitor reaction were obtained 3267400100029 by interpolating the evaluated values. 3267400100030 ERR-ANALYS (ERR-T) Total uncertainty. 3267400100031 (ERR-S,0.1,5.) Counting statistics. 3267400100032 (ERR-1,2.,3.) Detector efficiency (2%-3%) 3267400100033 (ERR-2) Weight of sample (0.1%) 3267400100034 (ERR-3) Self-absorption of gamma-ray (0.5%) 3267400100035 (ERR-4,0.,5.) Coincidence sum effect of cascade 3267400100036 gamma-rays (0%-5%) 3267400100037 (ERR-5,0.1,1.0) Uncertainties of irradiation, cooling 3267400100038 and measuring times (0.1%-1.0%) 3267400100039 (MONIT1-ERR) Uncertainties of standard cross section 3267400100040 of 93-Nb(n,2n)92m-Nb is 6.8, 6.8 and 5.0 mb at 13.5, 3267400100041 14.1 and 14.6 MeV, respectively. 3267400100042 (MONIT2-ERR) Uncertainties of standard cross section 3267400100043 of 27-Al(n,a)24-Na is 0.8, 0.6 and 0.6 mb at 13.5, 3267400100044 14.1 and 14.6 MeV, respectively. 3267400100045 CORRECTION The neutron flux was monitored by a uranium fission 3267400100046 chamber so that corrections were made for small 3267400100047 variations in the yield. The self-absorption of the 3267400100048 sample at a given gamma-energy, the coincidence sum 3267400100049 effect of cascade gamma-rays in the investigated 3267400100050 nuclide and in the counting geometry were taken into 3267400100051 account in data analysis, respectively. 3267400100052 STATUS (TABLE) Table 2 of Radiat.Phys.Chem.79(2010)1018 3267400100053 HISTORY (20110412C) Compiled by Jimin WANG(CNDC); 3267400100054 (20120227U) Corrected by Guochang CHEN (CNDC) 3267400100055 (20180419U) On. REFERENCE: IPC -> RPC 3267400100056 ENDBIB 54 0 3267400100057 COMMON 2 3 3267400100058 ERR-2 ERR-3 3267400100059 PER-CENT PER-CENT 3267400100060 0.1 0.5 3267400100061 ENDCOMMON 3 0 3267400100062 ENDSUBENT 61 0 3267400199999 SUBENT 32674002 20110412 31533267400200001 BIB 2 2 3267400200002 REACTION (78-PT-0(N,X)78-PT-195-M,,SIG) 3267400200003 DECAY-DATA (78-PT-195-M,4.02D,DG,98.85,0.1146) 3267400200004 ENDBIB 2 0 3267400200005 NOCOMMON 0 0 3267400200006 DATA 8 3 3267400200007 EN EN-ERR DATA ERR-T MONIT1 MONIT1-ERR 3267400200008 MONIT2 MONIT2-ERR 3267400200009 MEV MEV MB MB MB MB 3267400200010 MB MB 3267400200011 13.5 0.2 438. 16. 457.9 6.8 3267400200012 125.7 0.8 3267400200013 14.1 0.1 399. 14. 459.8 6.8 3267400200014 121.6 0.6 3267400200015 14.6 0.2 372. 13. 459.7 5.0 3267400200016 114.1 0.6 3267400200017 ENDDATA 10 0 3267400200018 ENDSUBENT 17 0 3267400299999 ENDENTRY 2 0 3267499999999