ENTRY 32760 20181120 31873276000000001 SUBENT 32760001 20181120 31873276000100001 BIB 15 45 3276000100002 TITLE Cross section measurements for 111Cd(n,p)111mAg, 3276000100003 106Cd(n,2n)105Cd, 110Cd(n,2n)109Cd, 3276000100004 116Cd(n,2n)115mCd and 116Cd(n,2n)115gCd reactions 3276000100005 AUTHOR (Kong Xiangzhong, Wang Yongchang, Yuan Jungqiang, 3276000100006 Yang Jingkang) 3276000100007 INSTITUTE (3CPRLNZ) 3276000100008 REFERENCE ((J,CNDP,13,13,1995)=(R,INDC(CPR)-34,13,1995)) 3276000100009 FACILITY (NGEN,3CPRLNZ) ZF-300-II intense neutron generator 3276000100010 INC-SOURCE (D-T) Neutron yield about 1 to 3E12 n/(4pi*s) . 3276000100011 Effective average energy of deuteron beam was about 3276000100012 125 keV and beam current was about 20 mA. The 3276000100013 thickness of T-Ti target was about 0.9 mg/cm2. The 3276000100014 samples were placed at the angles 0 to 140 deg 3276000100015 relative to the beam direction. The neutron energies 3276000100016 for various directions were determined by the cross 3276000100017 section ratios of 90Zr(n2n)89m+gZr and 93Nb(n,2n)92mNb.3276000100018 SAMPLE The samples of Al and Cd 20 mm in diameter and 0.1 mm 3276000100019 and 0.8 mm in thickness and 99.999% and 99.6% in 3276000100020 purity were made of natural metal foils. The Cd 3276000100021 sample in each group was sandwiched between two Al 3276000100022 foils. The groups of samples were placed at 5 to 28 cm 3276000100023 away from the neutron source. 3276000100024 DETECTOR (HPGE) CH8403 coaxial HPGe detector made in China 3276000100025 with a relative efficiency of 20% and an energy 3276000100026 resolution of 3 keV at 1.33 MeV. The efficiency of 3276000100027 detector was calibrated with the standard gamma 3276000100028 source SRM4275. The error in the absolute efficiency 3276000100029 curve at 2 cm was less than 1.5%, while the error of 3276000100030 the activity of the standard source was less than 1%. 3276000100031 METHOD (ACTIV) The samples were irradiated for 6.6 hours. 3276000100032 CORRECTION Some corrections were made for the gamma-ray 3276000100033 self-absorption in the samples, the cascade decay, 3276000100034 the counting geometry, and the effect of neutron 3276000100035 fluence fluctuation. 3276000100036 ERR-ANALYS (DATA-ERR) The major uncertainties were calculated as 3276000100037 quadratic sum of the errors such as the error of 3276000100038 reference cross sections, efficiency of Ge(Li) 3276000100039 detector, correction of sum peak, gamma-absorption in 3276000100040 sample, variation of neutron flux during irradiation, 3276000100041 counting statistics, gamma-ray intensities. 3276000100042 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3276000100043 DECAY-MON (11-NA-24,14.956HR,DG,1368.598,1.00) 3276000100044 STATUS (TABLE) Data were obtained from TABLE 2 of 3276000100045 Comm.Nucl.Data Prog,13,13,1995 3276000100046 HISTORY (20181120C) Compiled by Tao Xi(CNDC) 3276000100047 ENDBIB 45 0 3276000100048 NOCOMMON 0 0 3276000100049 ENDSUBENT 48 0 3276000199999 SUBENT 32760002 20181120 31873276000200001 BIB 3 3 3276000200002 REACTION (48-CD-111(N,P)47-AG-111,,SIG) 3276000200003 DECAY-DATA (47-AG-111-G,7.47D,DG,245.384,0.0124) 3276000200004 SAMPLE (48-CD-111,NAT=0.128) 3276000200005 ENDBIB 3 0 3276000200006 NOCOMMON 0 0 3276000200007 DATA 4 5 3276000200008 EN EN-ERR DATA DATA-ERR 3276000200009 MEV MEV MB MB 3276000200010 13.40 0.10 14.5 0.7 3276000200011 13.70 0.10 15.1 0.8 3276000200012 14.25 0.13 16.1 0.8 3276000200013 14.50 0.15 16.9 1.0 3276000200014 14.80 0.16 18.5 1.0 3276000200015 ENDDATA 7 0 3276000200016 ENDSUBENT 15 0 3276000299999 SUBENT 32760003 20181120 31873276000300001 BIB 4 4 3276000300002 REACTION (48-CD-106(N,2N)48-CD-105,,SIG) 3276000300003 DECAY-DATA (47-AG-105-G,41.29D,DG,280.52,0.310) 3276000300004 RAD-DET (47-AG-105-G,DG) 3276000300005 SAMPLE (48-CD-106,NAT=0.0125) 3276000300006 ENDBIB 4 0 3276000300007 NOCOMMON 0 0 3276000300008 DATA 4 5 3276000300009 EN EN-ERR DATA DATA-ERR 3276000300010 MEV MEV MB MB 3276000300011 13.40 0.10 1121. 61. 3276000300012 13.70 0.10 1146. 62. 3276000300013 14.25 0.13 1144. 62. 3276000300014 14.50 0.15 1150. 63. 3276000300015 14.80 0.16 1152. 63. 3276000300016 ENDDATA 7 0 3276000300017 ENDSUBENT 16 0 3276000399999 SUBENT 32760004 20181120 31873276000400001 BIB 3 3 3276000400002 REACTION (48-CD-110(N,2N)48-CD-109,,SIG) 3276000400003 DECAY-DATA (48-CD-109,1.2665YR,DG,88.0341,0.036) 3276000400004 SAMPLE (48-CD-110,NAT=0.1249) 3276000400005 ENDBIB 3 0 3276000400006 NOCOMMON 0 0 3276000400007 DATA 4 5 3276000400008 EN EN-ERR DATA DATA-ERR 3276000400009 MEV MEV MB MB 3276000400010 13.40 0.10 1232. 81. 3276000400011 13.70 0.10 1245. 85. 3276000400012 14.25 0.13 1235. 81. 3276000400013 14.50 0.15 1226. 79. 3276000400014 14.80 0.16 1221. 79. 3276000400015 ENDDATA 7 0 3276000400016 ENDSUBENT 15 0 3276000499999 SUBENT 32760005 20181120 31873276000500001 BIB 3 5 3276000500002 REACTION 1(48-CD-116(N,2N)48-CD-115-M,,SIG) 3276000500003 2(48-CD-116(N,2N)48-CD-115-G,,SIG) 3276000500004 DECAY-DATA (48-CD-115-M,44.6D,DG,933.847,0.0200) 3276000500005 (48-CD-115-G,2.228D,DG,527.910,0.275) 3276000500006 SAMPLE (48-CD-116,NAT=0.0749) 3276000500007 ENDBIB 5 0 3276000500008 NOCOMMON 0 0 3276000500009 DATA 6 5 3276000500010 EN EN-ERR DATA 1DATA-ERR 1DATA 2DATA-ERR 23276000500011 MEV MEV MB MB MB MB 3276000500012 13.40 0.10 652. 27. 826. 45.3276000500013 13.70 0.10 654. 27. 828. 45.3276000500014 14.25 0.13 658. 28. 822. 45.3276000500015 14.50 0.15 632. 26. 784. 44.3276000500016 14.80 0.16 626. 26. 784. 44.3276000500017 ENDDATA 7 0 3276000500018 ENDSUBENT 17 0 3276000599999 ENDENTRY 5 0 3276099999999