ENTRY 22000 19860703 00002200000000001 SUBENT 22000001 19860703 00002200000100001 BIB 14 26 2200000100002 INSTITUTE (2GERMUN) FIRST AUTHOR 2200000100003 (2FR ILL) SECOND AND THIRD AUTHORS, AND EXPERIMENTAL 2200000100004 SITE. 2200000100005 REFERENCE (J,ZP/A,322,669,8512) 2200000100006 AUTHOR (T.VON EGIDY,H.G.BOERNER,F.HOYLER) 2200000100007 TITLE -CROSS SECTIONS AND GAMMA-RAYS FROM MULTIPLE NEUTRON 2200000100008 CAPTURE IN EU-151 2200000100009 FACILITY (REAC) THE HIGH FLUX REACTOR OF THE INSTITUTE 2200000100010 LAUE LANGEVIN AT GRENOBLE. 2200000100011 INC-SOURCE (REAC) 2200000100012 INC-SPECT .MAXWELLIAN DISTRIBUTION. 2200000100013 SAMPLE .THREE DIFFERENT TARGETS WERE USED -- TARGET 1 -- 2200000100014 4.5 MG EU-151 OXIDE + 40 MG GRAPHITE POWDER, 2200000100015 TARGET 2 -- 6.8 MG EU-151 OXIDE + 56.4 MG GRAPHITE 2200000100016 POWDER, TARGET 3 -- 4.5 MG EU-151 OXIDE + 42.5 MG 2200000100017 GRAPHITE POWDER + 15.0 MG NACL. THE ENRICHMENT 2200000100018 OF EU-151 WAS 97.7 PC. 2200000100019 DETECTOR (GELI) IN THE PAIR SPECTROMETER. RESOLUTION 4.3 KEV 2200000100020 NEAR 6.3 MEV. 2200000100021 MONITOR (17-CL-35(N,G)17-CL-36,,SIG)FOR GAMMA-RAY ENERGY AND 2200000100022 RELATIVE NEUTRON INTENSITY CALIBRATIONS. 2200000100023 PART-DET (G ) 2200000100024 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2200000100025 HISTORY (860214C) Y.N. 2200000100026 (860703E) 2200000100027 ERR-ANALYS .NO DESCRIPTION GIVEN IN THE MAIN REFERENCE. 2200000100028 ENDBIB 26 0 2200000100029 NOCOMMON 0 0 2200000100030 ENDSUBENT 29 0 2200000199999 SUBENT 22000002 19860703 00002200000200001 BIB 4 7 2200000200002 REACTION (63-EU-152(N,G)63-EU-153,,SIG,,MXW) 2200000200003 ANALYSIS .THE VARIATION OF EU-CAPTURE LINES WITH THE 2200000200004 IRRADIATION TIME WAS USED TO DETERMINE THE 2200000200005 EFFECTIVE NEUTRON FLUX AND THE CROSS SECTION. 2200000200006 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2200000200007 HISTORY (860217C) Y.N. 2200000200008 (860703E) 2200000200009 ENDBIB 7 0 2200000200010 NOCOMMON 0 0 2200000200011 DATA 3 1 2200000200012 KT DATA DATA-ERR 2200000200013 DEG-K B B 2200000200014 3.2360E+02 7.9000E+03 1.3000E+03 2200000200015 ENDDATA 3 0 2200000200016 ENDSUBENT 15 0 2200000299999 SUBENT 22000003 19860703 00002200000300001 BIB 4 7 2200000300002 REACTION (63-EU-152(N,G)63-EU-153,,SIG,,,DERIV) 2200000300003 ANALYSIS .THE VARIATION OF EU-CAPTURE LINES WITH THE 2200000300004 IRRADIATION TIME WAS USED TO DETERMINE THE 2200000300005 EFFECTIVE NEUTRON FLUX AND THE CROSS SECTION. 2200000300006 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2200000300007 HISTORY (860217C) Y.N. 2200000300008 (860703E) 2200000300009 ENDBIB 7 0 2200000300010 NOCOMMON 0 0 2200000300011 DATA 3 1 2200000300012 EN DATA DATA-ERR 2200000300013 EV B B 2200000300014 2.5000E-02 1.0900E+04 1.8000E+03 2200000300015 ENDDATA 3 0 2200000300016 ENDSUBENT 15 0 2200000399999 SUBENT 22000004 19860703 00002200000400001 BIB 5 9 2200000400002 REACTION (63-EU-152(N,G)63-EU-153,,SIG,,MXW) 2200000400003 ANALYSIS .THE VARIATION OF EU-CAPTURE LINES WITH THE 2200000400004 IRRADIATION TIME WAS USED TO DETERMINE THE 2200000400005 EFFECTIVE NEUTRON FLUX AND THE CROSS SECTION. 2200000400006 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2200000400007 HISTORY (860217C) Y.N. 2200000400008 (860703E) 2200000400009 ERR-ANALYS (+DATA-ERR) PLUS DATA ERROR. 2200000400010 (-DATA-ERR) MINUS DATA ERROR. 2200000400011 ENDBIB 9 0 2200000400012 NOCOMMON 0 0 2200000400013 NODATA 0 0 ALL POINTS ELIMINATED FROM SET 2200000400014 ENDSUBENT 13 0 2200000499999 SUBENT 22000005 19860703 00002200000500001 BIB 5 9 2200000500002 REACTION (63-EU-152(N,G)63-EU-153,,SIG,,,DERIV) 2200000500003 ANALYSIS .THE VARIATION OF EU-CAPTURE LINES WITH THE 2200000500004 IRRADIATION TIME WAS USED TO DETERMINE THE 2200000500005 EFFECTIVE NEUTRON FLUX AND THE CROSS SECTION. 2200000500006 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2200000500007 HISTORY (860217C) Y.N. 2200000500008 (860703E) 2200000500009 ERR-ANALYS (+DATA-ERR) PLUS DATA ERROR. 2200000500010 (-DATA-ERR) MINUS DATA ERROR. 2200000500011 ENDBIB 9 0 2200000500012 NOCOMMON 0 0 2200000500013 NODATA 0 0 ALL POINTS ELIMINATED FROM SET 2200000500014 ENDSUBENT 13 0 2200000599999 SUBENT 22000006 19860904 00002200000600001 BIB 5 10 2200000600002 REACTION (63-EU-152(N,G)63-EU-153,,SIG,,MXW) 2200000600003 ANALYSIS .USING INTENSITY ARGUMENTS AND COMPARING AVERAGE 2200000600004 GAMMA-RAY INTENSITIES OF FIFTEEN CAPTURE LINES AND 2200000600005 FIVE LINES FOR GROUND AND METASTABLE STATES, THE 2200000600006 CAPTURE CROSS SECTION OF EU-152 WAS DETERMINED. 2200000600007 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2200000600008 HISTORY (860217C) Y.N. 2200000600009 (860703E) 2200000600010 ERR-ANALYS (+DATA-ERR) PLUS DATA ERROR. 2200000600011 (-DATA-ERR) MINUS DATA ERROR. 2200000600012 ENDBIB 10 0 2200000600013 NOCOMMON 0 0 2200000600014 NODATA 0 0 ALL POINTS ELIMINATED FROM SET 2200000600015 ENDSUBENT 14 0 2200000699999 SUBENT 22000007 19860904 00002200000700001 BIB 5 10 2200000700002 REACTION (63-EU-152(N,G)63-EU-153,,SIG,,,DERIV) 2200000700003 ANALYSIS .USING INTENSITY ARGUMENTS AND COMPARING AVERAGE 2200000700004 GAMMA-RAY INTENSITIES OF FIFTEEN CAPTURE LINES AND 2200000700005 FIVE LINES FOR GROUND AND METASTABLE STATES, THE 2200000700006 CAPTURE CROSS SECTION OF EU-152 WAS DETERMINED. 2200000700007 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2200000700008 HISTORY (860217C) Y.N. 2200000700009 (860703E) 2200000700010 ERR-ANALYS (+DATA-ERR) PLUS DATA ERROR. 2200000700011 (-DATA-ERR) MINUS DATA ERROR. 2200000700012 ENDBIB 10 0 2200000700013 NOCOMMON 0 0 2200000700014 NODATA 0 0 ALL POINTS ELIMINATED FROM SET 2200000700015 ENDSUBENT 14 0 2200000799999 ENDENTRY 7 0 2200099999999