ENTRY 31437 20100220 31443143700000001 SUBENT 31437001 20100220 31443143700100001 BIB 16 42 3143700100002 TITLE Isotopic effect in (n,p) reaction on ruthenium 3143700100003 AUTHOR (D.Kielan,A.Marcinkowski,U.Garuska) 3143700100004 INSTITUTE (3POLIPJ) 3143700100005 REFERENCE (J,NP/A,559,(3),333,199306) 3143700100006 FACILITY (VDG,3POLIPJ) 3143700100007 INC-SOURCE (D-T) Neutrons were produced by bombarding a T-Ti 3143700100008 target with 440 and 990 keV deuterons. The neutron 3143700100009 energy was selected by the angular position of the 3143700100010 sample with respect to the deuteron beam axis. 3143700100011 SAMPLE Spectrally pure metal, produced by Johnson and Matthey 3143700100012 contained in plexiglass cylinders, 1 cm high and 0.5 cm3143700100013 in diameter. 3143700100014 METHOD (ACTIV) 3143700100015 DETECTOR (GELI) 80 cm3 Ge(Li) detector 3143700100016 (CSICR) the fluctuations of the flux during 3143700100017 irradiation were monitoring continuously by 3143700100018 counting protons recoiling from a 3143700100019 polyethylene foil in a Cs(J) scintillator 3143700100020 MONITOR (26-FE-56(N,P)25-MN-56,,SIG) 3143700100021 for monitoring the absolute neutron flux 3143700100022 DECAY-MON (25-MN-56,2.58HR,DG,847.,.989) 3143700100023 MONIT-REF (,Z.Boedy,B,OKAMOTO,,29,198704) 3143700100024 CORRECTION The measured gamma-ray yields were corrected for 3143700100025 attenuation in the sample, sample holder and detector 3143700100026 housing. The correction for summing of pulses due to 3143700100027 simultaneous random detection of gamma-rays emitted 3143700100028 in cascade was determined with the program 'KORSUM'. 3143700100029 ERR-ANALYS (ERR-T) Both the statistical and systematic errors are 3143700100030 included. The latter incorporate uncertainties of 3143700100031 the following quantities: 3143700100032 (MONIT-ERR) reference cross section 2% 3143700100033 (ERR-1,,9.) integrat. of the pulse height spectrum =<9%3143700100034 (ERR-2) Ge(Li) efficiency 3% 3143700100035 (ERR-3,2.,5.) gamma-ray attenuation 2 - 5% 3143700100036 (ERR-4,,9.) correction for random detection of 3143700100037 gamma-rays emitted in cascade 2 - 5% 3143700100038 (ERR-5,,10.) multiparticle-emission correction 3143700100039 at neutron energies > 15.4 MeV =< 10% 3143700100040 HISTORY (19940609C) HW 3143700100041 (20100219A) SD:Updated to new date formats,lower case. 3143700100042 STATUS (TABLE) Data are from Table 2 of Nucl.Phys. A559, 3143700100043 no. 3, pp. 333 - 346. 3143700100044 ENDBIB 42 0 3143700100045 NOCOMMON 0 0 3143700100046 ENDSUBENT 45 0 3143700199999 SUBENT 31437002 20100220 31443143700200001 BIB 3 3 3143700200002 REACTION (44-RU-96(N,P)43-TC-96,,SIG) 3143700200003 DECAY-DATA (43-TC-96-G,4.28D,DG,778.,.9976) 3143700200004 COMMENT Measured sig-g + 0.9883 sig-m. 3143700200005 ENDBIB 3 0 3143700200006 NOCOMMON 0 0 3143700200007 DATA 4 8 3143700200008 EN EN-ERR DATA ERR-T 3143700200009 MEV MEV MB MB 3143700200010 13.0 0.4 236. 22. 3143700200011 13.4 0.2 214. 18. 3143700200012 13.9 0.3 188. 16. 3143700200013 14.5 0.3 172. 15. 3143700200014 15.0 0.3 154. 14. 3143700200015 15.4 0.2 146. 13. 3143700200016 15.9 0.5 138. 14. 3143700200017 16.6 0.1 111. 11. 3143700200018 ENDDATA 10 0 3143700200019 ENDSUBENT 18 0 3143700299999 SUBENT 31437003 20100220 31443143700300001 BIB 3 6 3143700300002 REACTION (44-RU-99(N,P)43-TC-99-M,,SIG) 3143700300003 DECAY-DATA (43-TC-99-M,6.02HR,DG,140.5,.8897) 3143700300004 CORRECTION The data are corrected for the calculated contribu- 3143700300005 tions of the Ru-102(n,a)Mo-99 reaction followed by 3143700300006 beta decay, and the Ru-100(n,np + pn + d)Tc-99 reac- 3143700300007 tions. 3143700300008 ENDBIB 6 0 3143700300009 NOCOMMON 0 0 3143700300010 DATA 4 8 3143700300011 EN EN-ERR DATA ERR-T 3143700300012 MEV MEV MB MB 3143700300013 13.0 0.4 12.9 2.2 3143700300014 13.4 0.2 12.8 1.8 3143700300015 13.9 0.3 11.2 1.7 3143700300016 14.5 0.3 12.0 1.9 3143700300017 15.0 0.3 11.9 1.9 3143700300018 15.4 0.2 11.4 1.9 3143700300019 15.9 0.5 12.3 2.3 3143700300020 16.6 0.1 12.1 2.6 3143700300021 ENDDATA 10 0 3143700300022 ENDSUBENT 21 0 3143700399999 SUBENT 31437004 20100220 31443143700400001 BIB 3 6 3143700400002 REACTION (44-RU-101(N,P)43-TC-101,,SIG) 3143700400003 DECAY-DATA (43-TC-101,14.2MIN,DG,306.8,0.88) 3143700400004 CORRECTION The data are corrected for the calculated contribu- 3143700400005 tions of the Ru-104(n,a)Mo-101 reaction followed by 3143700400006 beta decay, and the Ru-102(n,np + pn + d)Tc-101 reac- 3143700400007 tions. 3143700400008 ENDBIB 6 0 3143700400009 NOCOMMON 0 0 3143700400010 DATA 4 8 3143700400011 EN EN-ERR DATA ERR-T 3143700400012 MEV MEV MB MB 3143700400013 13.0 0.4 14.4 2.3 3143700400014 13.4 0.2 14.6 2.0 3143700400015 13.9 0.3 17.0 2.3 3143700400016 14.5 0.3 18.9 2.6 3143700400017 15.0 0.3 19.1 2.7 3143700400018 15.4 0.2 21.4 3.0 3143700400019 15.9 0.5 25.8 4.6 3143700400020 16.6 0.1 28.6 5.3 3143700400021 ENDDATA 10 0 3143700400022 ENDSUBENT 21 0 3143700499999 SUBENT 31437005 20100220 31443143700500001 BIB 2 2 3143700500002 REACTION (44-RU-102(N,P)43-TC-102-M,,SIG) 3143700500003 DECAY-DATA (43-TC-102-M,4.35MIN,DG,475.,.87) 3143700500004 ENDBIB 2 0 3143700500005 NOCOMMON 0 0 3143700500006 DATA 4 8 3143700500007 EN EN-ERR DATA ERR-T 3143700500008 MEV MEV MB MB 3143700500009 13.0 0.4 3.8 0.9 3143700500010 13.4 0.2 5.0 0.7 3143700500011 13.9 0.3 5.5 0.8 3143700500012 14.5 0.3 6.8 0.9 3143700500013 15.0 0.3 7.2 1.0 3143700500014 15.4 0.2 7.3 1.0 3143700500015 15.9 0.5 8.6 1.5 3143700500016 16.6 0.1 10.2 1.7 3143700500017 ENDDATA 10 0 3143700500018 ENDSUBENT 17 0 3143700599999 SUBENT 31437006 20100220 31443143700600001 BIB 2 2 3143700600002 REACTION (44-RU-102(N,A)42-MO-99,,SIG) 3143700600003 DECAY-DATA (42-MO-99,66.02HR,DG,140.5,.7720) 3143700600004 ENDBIB 2 0 3143700600005 NOCOMMON 0 0 3143700600006 DATA 4 5 3143700600007 EN EN-ERR DATA ERR-T 3143700600008 MEV MEV MB MB 3143700600009 13.4 0.2 5.6 0.3 3143700600010 13.9 0.3 6.0 0.3 3143700600011 14.5 0.3 7.1 0.3 3143700600012 15.0 0.3 7.6 0.4 3143700600013 15.4 0.2 7.9 0.4 3143700600014 ENDDATA 7 0 3143700600015 ENDSUBENT 14 0 3143700699999 SUBENT 31437007 20100220 31443143700700001 BIB 2 2 3143700700002 REACTION (44-RU-104(N,P)43-TC-104,,SIG) 3143700700003 DECAY-DATA (43-TC-104,18.2MIN,DG,358.,.89) 3143700700004 ENDBIB 2 0 3143700700005 NOCOMMON 0 0 3143700700006 DATA 4 8 3143700700007 EN EN-ERR DATA ERR-T 3143700700008 MEV MEV MB MB 3143700700009 13.0 0.4 3.0 0.6 3143700700010 13.4 0.2 3.4 0.6 3143700700011 13.9 0.3 4.3 0.6 3143700700012 14.5 0.3 5.2 0.8 3143700700013 15.0 0.3 6.5 0.8 3143700700014 15.4 0.2 6.7 0.9 3143700700015 15.9 0.5 9.4 1.5 3143700700016 16.6 0.1 13.4 2.2 3143700700017 ENDDATA 10 0 3143700700018 ENDSUBENT 17 0 3143700799999 ENDENTRY 7 0 3143799999999