ENTRY 30999 20230707 3099900000001 SUBENT 30999001 20230707 20240316 3099900100001 BIB 9 24 3099900100002 TITLE The study of isomeric cross sections for In(n,n') 3099900100003 reactions at 14 MeV. 3099900100004 AUTHOR (Lu Hanlin, Ke Wei, Zhao Wenrong, Yu Weixiang, 3099900100005 Yuan Xialin) 3099900100006 INSTITUTE (3CPRAEP) 3099900100007 REFERENCE (J,CNP,11,53,1989) 3099900100008 (R,INDC(CPR)-11,67,198803) 3099900100009 (R,INDC(CPR)-16,198908) Numerical data only. 3099900100010 FACILITY (CCW,3CPRAEP) IAE Cockcroft-Walton accelerator 3099900100011 INC-SOURCE (D-T) Neutron producing reaction was induced in a 3099900100012 solid T-Ti target (0.3-0.5 mg/cm**2) by 200 keV 3099900100013 deuterons. 3099900100014 DETECTOR (GELI) 3099900100015 STATUS (APRVD) 3099900100016 (TABLE,,Lu Hanlin+,J,CNP,11,53,1989) Table 3 3099900100017 HISTORY (19921008C) HW 3099900100018 (19930119A) HW.- Mispunches in subents 001, 002, 004 3099900100019 corrected, status altered.- 3099900100020 (19930510U) HW.- Page no.(Monit-)reference corrected in3099900100021 subents 001, 003 and 004.- 3099900100022 (20090912A) SD:Updated to new date formats,lower case. 3099900100023 Cosmetic changes, Common section and codes for 3099900100024 err-analys were added in every Subent 3099900100025 (20230707A) VT+On. Revision in 003-004 3099900100026 ENDBIB 24 0 3099900100027 NOCOMMON 0 0 3099900100028 ENDSUBENT 27 0 3099900199999 SUBENT 30999002 20090920 31413099900200001 BIB 7 29 3099900200002 SAMPLE Natural metal foil with chemical purity of more than 3099900200003 99.9%, 15 mm in diameter, placed at an angle 3099900200004 of 45 degrees with respect to the deuteron beam. 3099900200005 REACTION (49-IN-115(N,2N)49-IN-114-M,,SIG) 3099900200006 DECAY-DATA (49-IN-114-M,49.51D,DG,190.,.157) 3099900200007 METHOD (ACTIV,ASSOP) Absolute measurement. Neutron fluence was3099900200008 determined by associated alpha particle counting. 3099900200009 CORRECTION Source Correction % 3099900200010 ----------------------------------------------------- 3099900200011 - Neutron scattering by target system 1.2 3099900200012 - Neutron scattering by sample holder 0.3 3099900200013 - Neutron absorption in the target backing 1.6 3099900200014 - Gamma self absorption in the sample 7.2 3099900200015 - Sample area effect 1.0 3099900200016 - Variation of neutron yield 0.1 - 3.5 3099900200017 ERR-ANALYS (ERR-T) Source of uncertainty Uncertainty % 3099900200018 ----------------------------------------------------- 3099900200019 (ERR-1) Neutron scattering by target system 0.3 3099900200020 (ERR-2) Neutron scattering by sample holder 0.1 3099900200021 (ERR-3) Neutron absorption in the target backing 0.2 3099900200022 (ERR-4) Gamma self absorption in the sample 1.0 3099900200023 (ERR-5) Sample area effect 0.3 3099900200024 (ERR-6) Variation of neutron yield 0.1 3099900200025 (ERR-7) Detector efficiency or activity ratio 1.7 3099900200026 (ERR-8) Neutron fluence determination 1.2 3099900200027 (ERR-9,1.,3.) Neutron angular distribution 1. - 3.3099900200028 ----------------------------------------------------- 3099900200029 ERR-T 2.4 3099900200030 HISTORY (19930119A)HW.- Mispunches in decay-data corrected.- 3099900200031 ENDBIB 29 0 3099900200032 NOCOMMON 0 0 3099900200033 DATA 12 1 3099900200034 EN EN-ERR DATA ERR-T ERR-1 ERR-2 3099900200035 ERR-3 ERR-4 ERR-5 ERR-6 ERR-7 ERR-8 3099900200036 MEV MEV MB MB PER-CENT PER-CENT 3099900200037 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3099900200038 14.57 0.23 1296. 31. 0.3 0.1 3099900200039 0.2 1.0 0.3 0.1 1.7 1.2 3099900200040 ENDDATA 6 0 3099900200041 ENDSUBENT 40 0 3099900299999 SUBENT 30999003 20230707 20240316 3099900300001 BIB 10 31 3099900300002 REACTION (49-IN-115(N,INL)49-IN-115-M,,SIG) 3099900300003 DECAY-DATA (49-IN-115-M,4.486HR,DG,336.,.459) 3099900300004 SAMPLE Stripes of 15 * 5 mm in area and 0.5 mm in thickness. 3099900300005 MONITOR (49-IN-115(N,2N)49-IN-114-M,,SIG) 3099900300006 DECAY-MON (49-IN-114-M,49.51D,DG,190.,.1570) 3099900300007 MONIT-REF (30999002,LU HANLIN,J,CNP,11,(2),53,1989) 3099900300008 METHOD (ACTIV) 3099900300009 CORRECTION Source Correction % 3099900300010 ----------------------------------------------------- 3099900300011 - Neutrons produced by D(d,n)He-3 reaction .25 3099900300012 with deuterons accumulated on the target 3099900300013 - Neutron scattering by target system 7.2 3099900300014 - Neutron scattering by sample holder 0.8 3099900300015 - Gamma self absorption in the sample 4.0 3099900300016 - Sample area effect 0.6 3099900300017 ERR-ANALYS (ERR-T) Source of uncertainty Uncertainty % 3099900300018 ----------------------------------------------------- 3099900300019 (ERR-1) Neutrons produced by D(d,n)He-3 reaction 3099900300020 with deuterons accumulated in the target .05 3099900300021 (ERR-2) Neutron scattering by target system 2.2 3099900300022 (ERR-3) Neutron scattering by sample holder 0.4 3099900300023 (ERR-4) Gamma self absorption in the sample 0.4 3099900300024 (ERR-5) Sample area effect 0.1 3099900300025 (ERR-6) Variation of neutron yield 0.2 3099900300026 (ERR-7) Detector efficiency or activity ratio 1.5 3099900300027 (ERR-8) Standard cross section 2.4 3099900300028 (ERR-9) Neutron angular distribution 1.0 3099900300029 ----------------------------------------------------- 3099900300030 ERR-T 3.6 3099900300031 HISTORY (19930510U) HW.-Page no. Monit-ref. Corrected.- 3099900300032 (20230707A) VT+On. COMMON: EN-ERR = 0.23 MeV deleted. 3099900300033 ENDBIB 31 0 3099900300034 COMMON 12 6 3099900300035 EN-NRM MONIT MONIT-ERR ERR-1 ERR-2 ERR-3 3099900300036 ERR-4 ERR-5 ERR-6 ERR-7 ERR-8 ERR-9 3099900300037 MEV MB MB PER-CENT PER-CENT PER-CENT 3099900300038 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3099900300039 14.57 1296. 31. 0.05 2.2 0.43099900300040 0.4 0.1 0.2 1.5 2.4 1.03099900300041 ENDCOMMON 6 0 3099900300042 DATA 4 8 3099900300043 EN EN-ERR DATA ERR-T 3099900300044 MEV MEV MB MB 3099900300045 13.54 0.11 67.2 2.5 3099900300046 13.72 0.05 64.1 2.3 3099900300047 14.10 0.30 54.4 2.0 3099900300048 14.31 0.13 55.1 2.0 3099900300049 14.50 0.30 54.3 2.9 3099900300050 14.58 0.15 53.8 2.0 3099900300051 14.78 0.15 50.8 1.9 3099900300052 14.80 0.30 50.8 1.8 3099900300053 ENDDATA 10 0 3099900300054 ENDSUBENT 53 0 3099900399999 SUBENT 30999004 20230707 20240316 3099900400001 BIB 10 32 3099900400002 REACTION (49-IN-113(N,INL)49-IN-113-M,,SIG) 3099900400003 DECAY-DATA (49-IN-113-M,1.658HR,DG,391.,.6489) 3099900400004 SAMPLE Stripes of 15 * 5 mm in area and 0.5 mm in thickness. 3099900400005 MONITOR (49-IN-115(N,2N)49-IN-114-M,,SIG) 3099900400006 DECAY-MON (49-IN-114-M,49.51D,DG,190.,.1570) 3099900400007 MONIT-REF (30999002,LU HANLIN,J,CNP,11,(2),53,1989) 3099900400008 METHOD (ACTIV) 3099900400009 CORRECTION Source Correction % 3099900400010 ----------------------------------------------------- 3099900400011 - Neutrons produced by D(d,n)He-3 reaction 0.2 3099900400012 with deuterons accumulated on the target 3099900400013 - Neutrons scattering by target system 5.5 3099900400014 - Neutron scattering by sample holder 0.6 3099900400015 - Gamma self absorption in the sample 3.4 3099900400016 - Sample area effect 0.6 3099900400017 ERR-ANALYS (ERR-T) Source of uncertainty Uncertainty % 3099900400018 ----------------------------------------------------- 3099900400019 (ERR-1) Neutrons produced by D(d,n)He-3 reaction 3099900400020 with deuterons accumulated in the target .05 3099900400021 (ERR-2) Neutron scattering by target system 1.8 3099900400022 (ERR-3) Neutron scattering by sample holder 0.3 3099900400023 (ERR-4) Gamma self absorption in the sample 0.4 3099900400024 (ERR-5) Sample area effect 0.1 3099900400025 (ERR-6) Variation of neutron yield 0.2 3099900400026 (ERR-7) Detector efficiency or activity ratio 1.5 3099900400027 (ERR-8) Standard cross section 2.4 3099900400028 (ERR-9) Neutron angular distribution 1.0 3099900400029 ------------------------------------------------------ 3099900400030 ERR-T 3.4 3099900400031 HISTORY (19930119A)HW.- Corrections in data section.- 3099900400032 (19930510U) HW.-Page nr. Monit-ref. Corrected.- 3099900400033 (20230707A) VT+On. COMMON: EN-ERR = 0.23 MeV deleted. 3099900400034 ENDBIB 32 0 3099900400035 COMMON 12 6 3099900400036 EN-NRM MONIT MONIT-ERR ERR-1 ERR-2 ERR-3 3099900400037 ERR-4 ERR-5 ERR-6 ERR-7 ERR-8 ERR-9 3099900400038 MEV MB MB PER-CENT PER-CENT PER-CENT 3099900400039 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3099900400040 14.57 1296. 31. 0.05 1.8 0.33099900400041 0.4 0.1 0.2 1.5 2.4 1.03099900400042 ENDCOMMON 6 0 3099900400043 DATA 4 8 3099900400044 EN EN-ERR DATA ERR-T 3099900400045 MEV MEV MB MB 3099900400046 13.54 0.11 63.4 2.4 3099900400047 13.72 0.05 62.2 2.3 3099900400048 14.10 0.30 51.5 1.9 3099900400049 14.31 0.13 54.3 2.1 3099900400050 14.50 0.30 51.1 2.4 3099900400051 14.58 0.15 51.0 1.9 3099900400052 14.78 0.15 44.8 1.7 3099900400053 14.80 0.30 49.7 1.8 3099900400054 ENDDATA 10 0 3099900400055 ENDSUBENT 54 0 3099900499999 ENDENTRY 3 0 3099999999999