ENTRY 41506 20120120 Y0084150600000001 SUBENT 41506001 20120120 Y0084150600100001 BIB 16 38 4150600100002 TITLE Measurement of absolute intensities of some prompt 4150600100003 gamma-lines from the Zr-41, Nd-143, Hf-177 and 4150600100004 Sn-116, -118, -119, -120, -122, -124 (n,gamma) 4150600100005 reactions and isomeric cross-sections of Sn-123m, -125m4150600100006 by in-beam gamma-spectroscopy method. 4150600100007 AUTHOR (A.I.Egorov,Yu.E.Loginov,S.E.Malyutenkova) 4150600100008 INSTITUTE (4RUSLIN) 4150600100009 REFERENCE (J,ARI,65,1290,2007) 4150600100010 REL-REF (N,,A.I.Egorov+,J,NIM/A,545,296,2005) 4150600100011 (N,,A.I.Egorov+,R,LIJAF-2624,2005) 4150600100012 (N,,Yu.E.Loginov+,J,JRN/L,176,(5),361,1993) 4150600100013 For details of exp.arrangement, neutron spectrum, 4150600100014 detection efficiency and data analysis procedure 4150600100015 see REL-REFs. 4150600100016 FACILITY (REAC,4RUSLIN) WWR-M reactor 4150600100017 INC-SOURCE (REAC) WWR-M Reactor 4150600100018 INC-SPECT Neutron flux at target position about 2.E+7 n/cm**2/s.4150600100019 Neutron beam contains neither epithermal nor fast 4150600100020 neutrons. 4150600100021 DETECTOR (HPGE) High purity germanium detector for gamma-spectra4150600100022 measurement. 4150600100023 METHOD (GSPEC) In-beam gamma-spectroscopy. 4150600100024 MONITOR (13-AL-27(N,G)13-AL-28,,SIG) 4150600100025 DECAY-DATA (13-AL-28-G,2.24MIN,DG,1778.988,1.) 4150600100026 MONIT-REF (,Mughabghab+,B,NEUT.CS 1A,,1981) 4150600100027 ANALYSIS (AREA) Ratio of areas of gamma-lines from n,gamma 4150600100028 spectra of isotope in question and standard was used to4150600100029 determine absolute gamma-intensities or cross-sections.4150600100030 ERR-ANALYS (ERR-1) Experimental error consists of errors of 4150600100031 gamma-line areas measurement and gamma-efficiency of 4150600100032 spectrometer. 4150600100033 (ERR-T) Total error includes also isotope abundance and4150600100034 neutron capture cross-section uncertainties of 4150600100035 normalization. 4150600100036 HISTORY (20080218C) Compiled at the Center - CJD 4150600100037 (20101215U) Opening parenthesis was move in 12 column 4150600100038 in Subent 011. 4150600100039 (20120120A) NDS(VZ): REL-REF: ND/B->NDS in 011,012 4150600100040 ENDBIB 38 0 4150600100041 COMMON 4 3 4150600100042 EN EN-ERR MONIT MONIT-ERR 4150600100043 EV EV B B 4150600100044 0.028 0.002 0.231 0.003 4150600100045 ENDCOMMON 3 0 4150600100046 ENDSUBENT 45 0 4150600199999 SUBENT 41506002 20080218 41434150600200001 BIB 5 9 4150600200002 REACTION (40-ZR-91(N,G)40-ZR-92,,SPC) 4150600200003 Absolute intensity of gamma-line. 4150600200004 SAMPLE Target consists of mixture of precisely weighted 4150600200005 portions of oxides of natural element and aluminum as 4150600200006 standard. 4150600200007 EN-SEC (E,G) Gamma energy. 4150600200008 ANALYSIS In intensity determination the neutron radiative 4150600200009 capture cross-section values from MONIT-REF were used. 4150600200010 STATUS (TABLE) Table 1 of reference. 4150600200011 ENDBIB 9 0 4150600200012 NOCOMMON 0 0 4150600200013 DATA 5 1 4150600200014 E E-ERR DATA ERR-1 ERR-T 4150600200015 KEV KEV PC/INC PC/INC PC/INC 4150600200016 934.53 0.06 79. 10. 16. 4150600200017 ENDDATA 3 0 4150600200018 ENDSUBENT 17 0 4150600299999 SUBENT 41506003 20080218 41434150600300001 BIB 5 9 4150600300002 REACTION (60-ND-143(N,G)60-ND-144,,SPC) 4150600300003 Absolute intensity of gamma-lines. 4150600300004 SAMPLE Target consists of mixture of precisely weighted 4150600300005 portions of oxides of natural element and aluminum as 4150600300006 standard. 4150600300007 ANALYSIS In intensity determination the neutron radiative 4150600300008 capture cross-section values from MONIT-REF were used. 4150600300009 EN-SEC (E,G) Gamma energy. 4150600300010 STATUS (TABLE) Table 1 of reference. 4150600300011 ENDBIB 9 0 4150600300012 NOCOMMON 0 0 4150600300013 DATA 5 2 4150600300014 E E-ERR DATA ERR-1 ERR-T 4150600300015 KEV KEV PC/INC PC/INC PC/INC 4150600300016 618.06 0.03 34.2 1.4 1.7 4150600300017 696.54 0.01 77. 2. 3. 4150600300018 ENDDATA 4 0 4150600300019 ENDSUBENT 18 0 4150600399999 SUBENT 41506004 20080218 41434150600400001 BIB 5 9 4150600400002 REACTION (72-HF-177(N,G)72-HF-178,,SPC) 4150600400003 Absolute intensity of gamma-line. 4150600400004 SAMPLE Target consists of mixture of precisely weighted 4150600400005 portions of oxides of natural element and aluminum as 4150600400006 standard. 4150600400007 ANALYSIS In intensity determination the neutron radiative 4150600400008 capture cross-section values from MONIT-REF were used. 4150600400009 EN-SEC (E,G) Gamma energy. 4150600400010 STATUS (TABLE) Table 1 of reference. 4150600400011 ENDBIB 9 0 4150600400012 NOCOMMON 0 0 4150600400013 DATA 5 1 4150600400014 E E-ERR DATA ERR-1 ERR-T 4150600400015 KEV KEV PC/INC PC/INC PC/INC 4150600400016 213.42 0.01 37.4 1.3 1.6 4150600400017 ENDDATA 3 0 4150600400018 ENDSUBENT 17 0 4150600499999 SUBENT 41506005 20080218 41434150600500001 BIB 5 7 4150600500002 REACTION (50-SN-116(N,G)50-SN-117,,SPC) 4150600500003 Absolute intensity of gamma-lines. 4150600500004 SAMPLE Target consists of oxides of natural tin and aluminum.4150600500005 EN-SEC (E,G) Gamma energy. 4150600500006 ANALYSIS In intensity determination the neutron radiative 4150600500007 capture cross-section values from MONIT-REF were used. 4150600500008 STATUS (TABLE) Table 2 of reference. 4150600500009 ENDBIB 7 0 4150600500010 NOCOMMON 0 0 4150600500011 DATA 5 4 4150600500012 E E-ERR DATA ERR-1 ERR-T 4150600500013 KEV KEV PC/INC PC/INC PC/INC 4150600500014 52.97 0.09 5.8 0.8 1.5 4150600500015 158.56 0.01 80. 1. 17. 4150600500016 845.9 0.1 4.1 0.7 1.1 4150600500017 1004.5 0.1 16. 2. 4. 4150600500018 ENDDATA 6 0 4150600500019 ENDSUBENT 18 0 4150600599999 SUBENT 41506006 20080218 41434150600600001 BIB 5 7 4150600600002 REACTION (50-SN-118(N,G)50-SN-119,,SPC) 4150600600003 Absolute intensity of gamma-lines. 4150600600004 SAMPLE Target consists of oxides of natural tin and aluminum.4150600600005 EN-SEC (E,G) Gamma energy. 4150600600006 ANALYSIS In intensity determination the neutron radiative 4150600600007 capture cross-section values from MONIT-REF were used. 4150600600008 STATUS (TABLE) Table 2 of reference. 4150600600009 ENDBIB 7 0 4150600600010 NOCOMMON 0 0 4150600600011 DATA 5 5 4150600600012 E E-ERR DATA ERR-1 ERR-T 4150600600013 KEV KEV PC/INC PC/INC PC/INC 4150600600014 702.5 0.6 34. 1. 8. 4150600600015 988.6 0.7 2.9 0.2 0.7 4150600600016 1023.1 0.2 1.5 0.2 0.4 4150600600017 1171.4 0.2 38.3 0.4 8.7 4150600600018 1184.1 0.5 2.1 0.2 0.5 4150600600019 ENDDATA 7 0 4150600600020 ENDSUBENT 19 0 4150600699999 SUBENT 41506007 20080218 41434150600700001 BIB 5 7 4150600700002 REACTION (50-SN-119(N,G)50-SN-120,,SPC) 4150600700003 Absolute intensity of gamma-lines. 4150600700004 SAMPLE Target consists of oxides of natural tin and aluminum.4150600700005 EN-SEC (E,G) Gamma energy. 4150600700006 ANALYSIS In intensity determination the neutron radiative 4150600700007 capture cross-section values from MONIT-REF were used. 4150600700008 STATUS (TABLE) Table 2 of reference. 4150600700009 ENDBIB 7 0 4150600700010 NOCOMMON 0 0 4150600700011 DATA 5 6 4150600700012 E E-ERR DATA ERR-1 ERR-T 4150600700013 KEV KEV PC/INC PC/INC PC/INC 4150600700014 897.0 0.1 5.9 0.5 1.4 4150600700015 920.9 0.1 6.4 0.3 1.4 4150600700016 1065.6 0.2 3.0 0.4 0.8 4150600700017 1089.5 0.2 3.3 0.5 0.9 4150600700018 1225.8 0.2 1.9 0.4 0.6 4150600700019 1249.7 0.2 8.8 0.9 2.1 4150600700020 ENDDATA 8 0 4150600700021 ENDSUBENT 20 0 4150600799999 SUBENT 41506008 20080218 41434150600800001 BIB 5 7 4150600800002 REACTION (50-SN-120(N,G)50-SN-121,,SPC) 4150600800003 Absolute intensity of gamma-lines. 4150600800004 SAMPLE Target consists of oxides of natural tin and aluminum.4150600800005 EN-SEC (E,G) Gamma energy. 4150600800006 ANALYSIS In intensity determination the neutron radiative 4150600800007 capture cross-section values from MONIT-REF were used. 4150600800008 STATUS (TABLE) Table 3 of reference. 4150600800009 ENDBIB 7 0 4150600800010 NOCOMMON 0 0 4150600800011 DATA 5 5 4150600800012 E E-ERR DATA ERR-1 ERR-T 4150600800013 KEV KEV PC/INC PC/INC PC/INC 4150600800014 808.9 0.1 3.9 0.4 0.9 4150600800015 869.2 0.1 7.2 0.9 1.8 4150600800016 909.1 0.5 8.1 0.8 1.9 4150600800017 925.6 0.1 17.5 0.5 3.7 4150600800018 1102.1 0.4 6.9 0.5 0.6 4150600800019 ENDDATA 7 0 4150600800020 ENDSUBENT 19 0 4150600899999 SUBENT 41506009 20080218 41434150600900001 BIB 5 9 4150600900002 REACTION (50-SN-122(N,G)50-SN-123,,SPC) 4150600900003 Absolute intensity of gamma-lines. 4150600900004 SAMPLE Target consists of oxides of natural tin and aluminum.4150600900005 EN-SEC (E,G) Gamma energy. 4150600900006 ANALYSIS Absolute intensities were determined using the isomeric4150600900007 neutron radiative capture cross-section values measured4150600900008 in this experiment see SUBENT 011. 4150600900009 STATUS (TABLE) Table 3 of reference. 4150600900010 (DEP,41506011) 4150600900011 ENDBIB 9 0 4150600900012 NOCOMMON 0 0 4150600900013 DATA 5 3 4150600900014 E E-ERR DATA ERR-1 ERR-T 4150600900015 KEV KEV PC/INC PC/INC PC/INC 4150600900016 125.76 0.04 28.4 0.6 1.1 4150600900017 769.5 0.2 6.2 1.5 1.6 4150600900018 1019.7 0.1 24.7 3.6 3.7 4150600900019 ENDDATA 5 0 4150600900020 ENDSUBENT 19 0 4150600999999 SUBENT 41506010 20080218 41434150601000001 BIB 5 9 4150601000002 REACTION (50-SN-124(N,G)50-SN-125,,SPC) 4150601000003 Absolute intensity of gamma-lines. 4150601000004 SAMPLE Target consists of oxides of natural tin and aluminum.4150601000005 EN-SEC (E,G) Gamma energy. 4150601000006 ANALYSIS Absolute intensities were determined using the isomeric4150601000007 neutron radiative capture cross-section values measured4150601000008 in this experiment see SUBENT 012. 4150601000009 STATUS (TABLE) Table 3 of reference. 4150601000010 (DEP,41506012) 4150601000011 ENDBIB 9 0 4150601000012 NOCOMMON 0 0 4150601000013 DATA 5 1 4150601000014 E E-ERR DATA ERR-1 ERR-T 4150601000015 KEV KEV PC/INC PC/INC PC/INC 4150601000016 187.63 0.3 43.8 1.7 1.8 4150601000017 ENDDATA 3 0 4150601000018 ENDSUBENT 17 0 4150601099999 SUBENT 41506011 20120120 Y0084150601100001 BIB 6 12 4150601100002 REACTION (50-SN-122(N,G)50-SN-123-M,,SIG) 4150601100003 Neutron radiative capture cross-section 4150601100004 SAMPLE Target consists of oxides of natural tin and aluminum.4150601100005 DECAY-DATA (50-SN-123-M,40.08MIN,DG,160.3,0.857) 4150601100006 Data from REL-REF about beta-decay of isomer were 4150601100007 used for cross-section determination. Gamma-ray was 4150601100008 observed in measured gamma-spectrum in equilibrium 4150601100009 with capture radiation. 4150601100010 REL-REF (R,,J.Katakura,J,NDS,70,533,1993) Reference for decay 4150601100011 data of Sn-123m. 4150601100012 STATUS (TABLE) Text of reference, p.1291. 4150601100013 HISTORY (20120120A) NDS(VZ): REL-REF: ND/B->NDS 4150601100014 ENDBIB 12 0 4150601100015 NOCOMMON 0 0 4150601100016 DATA 2 1 4150601100017 DATA DATA-ERR 4150601100018 B B 4150601100019 0.172 0.005 4150601100020 ENDDATA 3 0 4150601100021 ENDSUBENT 20 0 4150601199999 SUBENT 41506012 20120120 Y0084150601200001 BIB 6 12 4150601200002 REACTION (50-SN-122(N,G)50-SN-123-M,,SIG) 4150601200003 Neutron radiative capture cross-section. 4150601200004 SAMPLE Target consists of oxides of natural tin and aluminum.4150601200005 DECAY-DATA (50-SN-125-M,9.52MIN,DG,332.04,0.972) 4150601200006 Data from REL-REF about beta-decay of isomer were 4150601200007 used for cross-section determination. Gamma-ray was 4150601200008 observed in measured gamma-spectrum in equilibrium 4150601200009 with capture radiation. 4150601200010 REL-REF (R,,J.Katakura,J,NDS,86,955,1999) Reference for decay 4150601200011 data of Sn-125m. (Issue A125). 4150601200012 STATUS (TABLE) Text of reference, p.1291. 4150601200013 HISTORY (20120120A) NDS(VZ): REL-REF: ND/B->NDS 4150601200014 ENDBIB 12 0 4150601200015 NOCOMMON 0 0 4150601200016 DATA 2 1 4150601200017 DATA DATA-ERR 4150601200018 B B 4150601200019 0.150 0.005 4150601200020 ENDDATA 3 0 4150601200021 ENDSUBENT 20 0 4150601299999 ENDENTRY 12 0 4150699999999