ENTRY 30940 20090913 31413094000000001 SUBENT 30940001 20090913 31413094000100001 BIB 17 62 3094000100002 TITLE Cross sections of the (n,p) reaction on zirconium 3094000100003 isotopes 3094000100004 AUTHOR (A.Marcinkowski,U.Garuska,H.M.Hoang,D.Kielan, 3094000100005 B.Zwieglinski) 3094000100006 INSTITUTE (3POLIPJ) 3094000100007 REFERENCE (J,NP/A,510,93,1990) Summary 3094000100008 (C,86DUBROV,,262,198605) Graphs only 3094000100009 SAMPLE The samples of natural zirconium were 3094000100010 spectroscopically pure metallic cylinders 3094000100011 MONITOR (26-FE-56(N,P)25-MN-56,,SIG) 3094000100012 MONIT-REF (,D.E.CULLEN+,R,IAEA-NDS-41,1,1982) 3094000100013 FACILITY (VDG,3POLIPJ) 3 MeV Van de Graff 3094000100014 INC-SOURCE (D-T) 3094000100015 *The monoenergetic neutrons were obtained by bombarding3094000100016 tritium absorbed in a thin layer of titanium deposited3094000100017 on a Cu backing with deuterons accelerated up to 1 MeV3094000100018 *The energy of neutrons was selected by the choice of 3094000100019 the emission angle. 3094000100020 *The neutron energy spread was evaluated from the 3094000100021 effective energy distributions of neutrons incident 3094000100022 on the samples,wich were calculated by the Monte Carlo3094000100023 method. 3094000100024 PART-DET (DG) 3094000100025 METHOD (ACTIV) 3094000100026 DETECTOR (GELI) 80 cm3 volume 3094000100027 The relative efficiency was determined with use of 3094000100028 standard radioactive sources Yb-169 and Ra-226. 3094000100029 (CSICR) The fluctuations of the neutron flux during 3094000100030 irradiation were monitored by counting protons 3094000100031 recoiling from a thin polyethylene foil,with the use 3094000100032 of Cs(Tl) scintillation crystal in a multiscaler mode. 3094000100033 CORRECTION * The final results were corrected for summing of 3094000100034 pulses in the Ge(Li) crystal due to cascading 3094000100035 gamma-rays in the samples. 3094000100036 * Corrections due contributions of multiparticle 3094000100037 emission,as well as for deuteron emission in measured3094000100038 activities were taken into account. 3094000100039 ERR-ANALYS (ERR-T) Given error was due to a statistical error and 3094000100040 several systematic errors among which the most 3094000100041 important are : 3094000100042 (ERR-1) Uncertanty of the reference cross section 3% 3094000100043 (ERR-2) Error in the integration of the pulse height 3094000100044 spectrum (up to) 11% 3094000100045 (ERR-3) Relative efficiency for detections 3094000100046 of gamma-rays 3% 3094000100047 (ERR-4) Gamma-ray attenuation uncertainty 2% 3094000100048 Another 10 % error was added due to the correction for 3094000100049 multiparticle emission at neutron energies > 15.5 MeV 3094000100050 ANALYSIS When reactions on different target isotopes lead to the3094000100051 same product nucleus a set of differential equations, 3094000100052 describing the production and the decay of the nuclei 3094000100053 of interest have been solved in order to obtain 3094000100054 relations between the investigated and the interfering 3094000100055 reaction cross section;in relation with this were 3094000100056 measured cross section for reactions 3094000100057 Zr-94(n,a)Sr-91 and Zr-90(n,a)Sr-87-m 3094000100058 STATUS (TABLE) Data taken from Nucl.Phys.,A510(1990),pag.93, 3094000100059 Table 2. 3094000100060 HISTORY (19900530C) VOF.- 3094000100061 (20090912A) SD:Updated to new date formats,lower case. 3094000100062 Cosmetic changes, codes for partial uncertainties and 3094000100063 data to COMMON section were added in Subent 001. 3094000100064 ENDBIB 62 0 3094000100065 COMMON 4 3 3094000100066 ERR-1 ERR-2 ERR-3 ERR-4 3094000100067 PER-CENT PER-CENT PER-CENT PER-CENT 3094000100068 3.0 11.0 3.0 2.0 3094000100069 ENDCOMMON 3 0 3094000100070 ENDSUBENT 69 0 3094000199999 SUBENT 30940002 20090913 31413094000200001 BIB 2 2 3094000200002 REACTION (40-ZR-90(N,P)39-Y-90-M,,SIG) 3094000200003 DECAY-DATA (39-Y-90-M,3.19HR,DG,480.,0.910) 3094000200004 ENDBIB 2 0 3094000200005 NOCOMMON 0 0 3094000200006 DATA 4 8 3094000200007 EN EN-ERR DATA ERR-T 3094000200008 MEV MEV MB MB 3094000200009 13.4 0.4 9.800 1.200 3094000200010 13.6 0.3 11.6 1.300 3094000200011 14.2 0.3 11.7 1.400 3094000200012 14.8 0.3 11.7 1.400 3094000200013 15.2 0.2 11.9 1.500 3094000200014 15.4 0.2 11.8 1.400 3094000200015 15.9 0.5 12.0 1.700 3094000200016 16.6 0.1 12.1 2.000 3094000200017 ENDDATA 10 0 3094000200018 ENDSUBENT 17 0 3094000299999 SUBENT 30940003 20090913 31413094000300001 BIB 2 2 3094000300002 REACTION (40-ZR-91(N,P)39-Y-91-M,,SIG) 3094000300003 DECAY-DATA (39-Y-91-M,49.7MIN,DG,556.,0.949) 3094000300004 ENDBIB 2 0 3094000300005 NOCOMMON 0 0 3094000300006 DATA 4 8 3094000300007 EN EN-ERR DATA ERR-T 3094000300008 MEV MEV MB MB 3094000300009 13.4 0.4 13.1 1.900 3094000300010 13.6 0.3 14.8 1.600 3094000300011 14.2 0.3 16.2 1.700 3094000300012 14.8 0.3 17.1 1.700 3094000300013 15.2 0.2 17.3 1.800 3094000300014 15.4 0.2 16.0 1.900 3094000300015 15.9 0.5 18.3 2.900 3094000300016 16.6 0.1 22.8 3.900 3094000300017 ENDDATA 10 0 3094000300018 ENDSUBENT 17 0 3094000399999 SUBENT 30940004 20090913 31413094000400001 BIB 2 2 3094000400002 REACTION (40-ZR-92(N,P)39-Y-92,,SIG) 3094000400003 DECAY-DATA (39-Y-92,3.54HR,DG,935.,0.139) 3094000400004 ENDBIB 2 0 3094000400005 NOCOMMON 0 0 3094000400006 DATA 4 8 3094000400007 EN EN-ERR DATA ERR-T 3094000400008 MEV MEV MB MB 3094000400009 13.4 0.4 14.3 2.600 3094000400010 13.6 0.3 18.4 2.400 3094000400011 14.2 0.3 18.3 2.300 3094000400012 14.8 0.3 17.6 2.300 3094000400013 15.2 0.2 20.8 2.600 3094000400014 15.4 0.2 21.0 2.600 3094000400015 15.9 0.5 22.5 3.300 3094000400016 16.6 0.1 21.9 3.300 3094000400017 ENDDATA 10 0 3094000400018 ENDSUBENT 17 0 3094000499999 SUBENT 30940005 20090913 31413094000500001 BIB 2 2 3094000500002 REACTION (40-ZR-94(N,P)39-Y-94,,SIG) 3094000500003 DECAY-DATA (39-Y-94,18.7MIN,DG,919.,0.560) 3094000500004 ENDBIB 2 0 3094000500005 NOCOMMON 0 0 3094000500006 DATA 4 8 3094000500007 EN EN-ERR DATA ERR-T 3094000500008 MEV MEV MB MB 3094000500009 13.4 0.4 4.100 1.500 3094000500010 13.6 0.3 6.000 0.800 3094000500011 14.2 0.3 5.200 0.800 3094000500012 14.8 0.3 7.400 0.900 3094000500013 15.2 0.2 8.300 1.000 3094000500014 15.4 0.2 8.600 1.000 3094000500015 15.9 0.5 7.300 1.600 3094000500016 16.6 0.1 8.900 1.900 3094000500017 ENDDATA 10 0 3094000500018 ENDSUBENT 17 0 3094000599999 SUBENT 30940006 20090913 31413094000600001 BIB 2 2 3094000600002 REACTION (40-ZR-90(N,A)38-SR-87-M,,SIG) 3094000600003 DECAY-DATA (38-SR-87-M,2.8HR,DG,388.,0.820) 3094000600004 ENDBIB 2 0 3094000600005 NOCOMMON 0 0 3094000600006 DATA 4 8 3094000600007 EN EN-ERR DATA ERR-T 3094000600008 MEV MEV MB MB 3094000600009 13.4 0.4 2.600 0.400 3094000600010 13.6 0.3 3.300 0.400 3094000600011 14.2 0.3 3.400 0.400 3094000600012 14.8 0.3 3.700 0.500 3094000600013 15.2 0.2 4.000 0.600 3094000600014 15.4 0.2 4.000 0.500 3094000600015 15.9 0.5 3.300 0.600 3094000600016 16.6 0.1 3.600 0.500 3094000600017 ENDDATA 10 0 3094000600018 ENDSUBENT 17 0 3094000699999 SUBENT 30940007 20090913 31413094000700001 BIB 2 2 3094000700002 REACTION (40-ZR-94(N,A)38-SR-91,,SIG) 3094000700003 DECAY-DATA (38-SR-91,9.48HR,DG,1024.,0.330) 3094000700004 ENDBIB 2 0 3094000700005 NOCOMMON 0 0 3094000700006 DATA 4 8 3094000700007 EN EN-ERR DATA ERR-T 3094000700008 MEV MEV MB MB 3094000700009 13.4 0.4 3.500 0.800 3094000700010 13.6 0.3 4.000 0.600 3094000700011 14.2 0.3 4.100 0.600 3094000700012 14.8 0.3 4.800 0.700 3094000700013 15.2 0.2 4.800 0.700 3094000700014 15.4 0.2 4.600 0.600 3094000700015 15.9 0.5 5.300 1.100 3094000700016 16.6 0.1 5.200 1.000 3094000700017 ENDDATA 10 0 3094000700018 ENDSUBENT 17 0 3094000799999 ENDENTRY 7 0 3094099999999