ENTRY 22446 20181225 22732244600000001 SUBENT 22446001 20181225 22732244600100001 BIB 15 29 2244600100002 TITLE Measurement of direct neutron capture by neutron-rich 2244600100003 sulfur isotopes 2244600100004 AUTHOR (H.Beer,C.Coceva,R.Hofinger,P.Mohr,H.Oberhummer, 2244600100005 P.V.Sedyshev,Yu.P.Popov) 2244600100006 INSTITUTE (2GERKFK) Beer 2244600100007 (2ITYBOL) Coceva 2244600100008 (2AUSTHV) Hofinger, Mohr, Oberhummer 2244600100009 (4ZZZDUB) Sedyshev, Popov 2244600100010 (2BLGMOL) Experimental Site 2244600100011 REFERENCE (J,NP/A,621,235,1997) Main Reference 2244600100012 FACILITY (REAC,2BLGMOL) Reactor BR1 of the "Studiecentrum 2244600100013 voor Kernenergie" in MOL, Belgium 2244600100014 INC-SOURCE (REAC) 2244600100015 INC-SPECT Thermal Spectrum of the Reactor BR1 2244600100016 DETECTOR (GE-IN) 2244600100017 MONITOR Neutron flux and efficiency of the detector were 2244600100018 determined in a calibration run on 35Cl. 2244600100019 METHOD (ACTIV,SITA) Activation method for Single-Target 2244600100020 irradiation 2244600100021 SAMPLE Sample of elemental sulfur, total weight 313.6 mg, 2244600100022 contained in a teflon cylinder of 6 mm inner diam. 2244600100023 was enriched in 34S by 93.26% and in 36S by 5.933%. 2244600100024 ADD-RES (STRUC,THEO) 2244600100025 ERR-ANALYS (ERR-SYS) Systematic error 2244600100026 (DATA-ERR) Errors are not specified 2244600100027 STATUS (TABLE) Tables 1,2 from Nucl.Phys.A621(1997)235 2244600100028 HISTORY (20000122C) + + Compiled by S.M. 2244600100029 (20000122U) Last checking has been done. 2244600100030 (20181225A) SD: Major corrections in all Subents. 2244600100031 ENDBIB 29 0 2244600100032 COMMON 1 3 2244600100033 EN-DUMMY 2244600100034 EV 2244600100035 2.53E-02 2244600100036 ENDCOMMON 3 0 2244600100037 ENDSUBENT 36 0 2244600199999 SUBENT 22446002 20181225 22732244600200001 BIB 4 9 2244600200002 REACTION (16-S-34(N,G)16-S-35,PAR,SIG,,MXW) Sigma for gamma 2244600200003 production 2244600200004 CORRECTION The data were corrected for multiple neutron 2244600200005 scattering (5.6%). 2244600200006 MISC-COL (MISC) Gamma transition energy 2244600200007 HISTORY (20181225A) SD: 0.98 -> 1.4 mb in col. DATA-ERR at 2244600200008 E=2082.6 MeV. CORRRECTION added. Col.ERR-SYS added. 2244600200009 SF7=G deleted from REACTION code. E-LVL added; values 2244600200010 from col. E moved to MISC. 2244600200011 ENDBIB 9 0 2244600200012 COMMON 1 3 2244600200013 ERR-SYS 2244600200014 PER-CENT 2244600200015 3.6 2244600200016 ENDCOMMON 3 0 2244600200017 DATA 4 5 2244600200018 E-LVL DATA DATA-ERR MISC 2244600200019 KEV MB MB KEV 2244600200020 4963. 26.9 1.1 2022.9 2244600200021 4903. 37.2 1.4 2082.6 2244600200022 4189. 14.6 0.7 2796.8 2244600200023 3802. 16.9 0.8 3184.0 2244600200024 2348. 148.6 5.5 4638.2 2244600200025 ENDDATA 7 0 2244600200026 ENDSUBENT 25 0 2244600299999 SUBENT 22446003 20181225 22732244600300001 BIB 5 12 2244600300002 REACTION 1(16-S-34(N,G)16-S-35,,SIG,,MXW) 2244600300003 2(16-S-34(N,G)16-S-35,,SIG,,MXW) 2244600300004 ANALYSIS 1The total capture cross section was calculated from 2244600300005 the sum of primary transitions. 2244600300006 2The total capture cross section was calculated from 2244600300007 the sum of secondary ground state transition 2244600300008 STATUS 1(DEP,22446002) 2244600300009 CORRECTION The data were corrected for multiple neutron 2244600300010 scattering (5.6%). 2244600300011 HISTORY (20181225A) SD: ANALYSIS,CORRECTION added. Col.ERR-SYS 2244600300012 added. Values corrected according to the Tbl.1 of 2244600300013 Nucl.Phys.A621(1997)235. 2244600300014 ENDBIB 12 0 2244600300015 COMMON 1 3 2244600300016 ERR-SYS 2244600300017 PER-CENT 2244600300018 3.6 2244600300019 ENDCOMMON 3 0 2244600300020 DATA 4 1 2244600300021 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 2244600300022 MB MB MB MB 2244600300023 244.3 8.8 249.3 9.0 2244600300024 ENDDATA 3 0 2244600300025 ENDSUBENT 24 0 2244600399999 SUBENT 22446004 20181225 22732244600400001 BIB 4 8 2244600400002 REACTION (16-S-36(N,G)16-S-37,PAR,SIG,,MXW) Sigma for gamma 2244600400003 production 2244600400004 CORRECTION The data were corrected for multiple neutron 2244600400005 scattering (7%). 2244600400006 MISC-COL (MISC) Gamma transition energy 2244600400007 HISTORY (20181225A) SD: CORRRECTION added. Col.ERR-SYS added. 2244600400008 SF7=G deleted from REACTION code. E-LVL added; values 2244600400009 from col. E moved to MISC. 2244600400010 ENDBIB 8 0 2244600400011 COMMON 1 3 2244600400012 ERR-SYS 2244600400013 PER-CENT 2244600400014 4.8 2244600400015 ENDCOMMON 3 0 2244600400016 DATA 4 3 2244600400017 E-LVL DATA DATA-ERR MISC 2244600400018 KEV MB MB KEV 2244600400019 2638. 54.8 6.9 1665.7 2244600400020 1992. 31.3 5.1 2311.6 2244600400021 647. 153.3 9.9 3657.3 2244600400022 ENDDATA 5 0 2244600400023 ENDSUBENT 22 0 2244600499999 SUBENT 22446005 20181225 22732244600500001 BIB 5 12 2244600500002 REACTION 1(16-S-36(N,G)16-S-37,,SIG,,MXW) 2244600500003 2(16-S-36(N,G)16-S-37,,SIG,,MXW) 2244600500004 ANALYSIS 1The total capture cross section was calculated from 2244600500005 the sum of primary transitions. 2244600500006 2The total capture cross section was calculated from 2244600500007 the sum of secondary ground state transition 2244600500008 CORRECTION The data were corrected for multiple neutron 2244600500009 scattering (7%). 2244600500010 STATUS (DEP,22446004) 2244600500011 HISTORY (20181225A) SD: ANALYSIS, CORRECTION added. Col.ERR-SYS2244600500012 added. Values corrected according to the Tbl.1 of 2244600500013 Nucl.Phys.A621(1997)235. 2244600500014 ENDBIB 12 0 2244600500015 COMMON 1 3 2244600500016 ERR-SYS 2244600500017 PER-CENT 2244600500018 4.8 2244600500019 ENDCOMMON 3 0 2244600500020 DATA 4 1 2244600500021 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 2244600500022 MB MB MB MB 2244600500023 239. 15. 249. 14. 2244600500024 ENDDATA 3 0 2244600500025 ENDSUBENT 24 0 2244600599999 ENDENTRY 5 0 2244699999999