ENTRY 32591 20100328 31473259100000001 SUBENT 32591001 20100328 31473259100100001 BIB 15 42 3259100100002 TITLE The cross section measurements for Co-59(n,p)Fe-59, 3259100100003 Co-59(n,alpha)Mn-56 and Co-59(n,2n)Co-58 reaction 3259100100004 INSTITUTE (3CPRBJG,3CPRAEP) 3259100100005 REFERENCE (J,PHE,14,(6),542,199006) in Chinese 3259100100006 (R,INDC(CPR)-16,39,199008) 3259100100007 AUTHOR (Li Tingyan,Shi Zhaomin,Lu Hanlin,Zhao Wenrong, 3259100100008 Yu Weixiang,Yuan Xialin) 3259100100009 FACILITY (CCW,3CPRAEP) 600 KV Cockcroft-Walton accelerator 3259100100010 (VDG,3CPRAEP) 2.5 mV Van de Graaff 3259100100011 INC-SOURCE (D-T) En=13-15 MeV neutrons produced by 200 keV 3259100100012 deuterons from Cockcroft-Walton accelerator bombarding 3259100100013 the titanium tritide target. 3259100100014 Below 13 MeV and above 15 MeV neutrons produced by 3259100100015 Van de Graaff. 3259100100016 SAMPLE Natural cobalt, purity better than 99.9%, 3259100100017 diameter=20 mm, thickness about 1.1 mm, weight about 3259100100018 2900 mg. 3259100100019 METHOD (ACTIV) 3259100100020 DETECTOR (GELI) A 130 cm3 Ge-Li detector was used for gamma ray 3259100100021 from residual nuclei measurement, gamma-ray standard 3259100100022 sources series with gamma energy from 0.1 MeV to 1.5MeV3259100100023 was used for detector efficiency calibration, the 3259100100024 efficiency curve was obtained by the Least-Square 3259100100025 method. 3259100100026 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3259100100027 MONIT-REF (,Tagesen+,B,PH-DAT,,13-1,1989) 3259100100028 DECAY-MON (11-NA-24,15.02HR,DG,1368.,0.99994) 3259100100029 CORRECTION Corrections were made for 3259100100030 detection efficiency 3259100100031 gamma-cascade effect 3259100100032 gamma self-absorption in sample 3259100100033 gamma-ray intensity 3259100100034 neutrons scattering in sample and target 3259100100035 neutron flux fluctuation 3259100100036 STATUS (TABLE) Data taken from Table 2 of High Energy Physics 3259100100037 and Nuclear Physics, 14(6), 542, 1990. 3259100100038 (APRVD) proof copy was approved by author and authors 3259100100039 corrections have been entered. 3259100100040 HISTORY (19930416C) Compiled by Liang Qichang (CNDC) 3259100100041 (19970421U) HW.- PART-DET deleted in subents 002-004.- 3259100100042 (19971009A) HW.- Reference added in subent 001. 3259100100043 (20100328A) SD:Updated to new date formats,lower case. 3259100100044 ENDBIB 42 0 3259100100045 NOCOMMON 0 0 3259100100046 ENDSUBENT 45 0 3259100199999 SUBENT 32591002 20100328 31473259100200001 BIB 5 37 3259100200002 REACTION (27-CO-59(N,P)26-FE-59,,SIG) 3259100200003 DECAY-DATA (26-FE-59,44.496D,DG,1099.,0.565) 3259100200004 ERR-ANALYS (ERR-T) Main error sources as follows: 3259100200005 (ERR-S,0.6,3.) statistical of gamma-ray from 3259100200006 residual nuclei. 3259100200007 (DATA-ERR,0.5,2.7) statist. of gamma-ray from monitor 3259100200008 (ERR-2) 3.8% detector efficiency for gamma-ray from 3259100200009 residual nuclei. 3259100200010 (ERR-3) 1.0% detector efficiency for gamma-ray from 3259100200011 monitor 3259100200012 (MONIT-ERR,0.4,2.1) uncertainty in monitor reaction 3259100200013 (ERR-5) 1.0% correction for residual nuclei gamm 3259100200014 ray self-absorption in sample. 3259100200015 (ERR-6) 0.1% correction for Na-24 gamma-ray self 3259100200016 absorption in sample. 3259100200017 (ERR-7,0.07,0.09) correction for neutron flux 3259100200018 fluctuation of residual nuclei. 3259100200019 (ERR-8,0.15,0.3) correction for neutron flux 3259100200020 fluctuation of Na-24. 3259100200021 (ERR-9,0.0033,0.0075) nuclides number in sample. 3259100200022 (ERR-10,0.012,0.015) nuclides number in Al-27 monitor 3259100200023 (ERR-11) 0.1% correction for neutron scattering in 3259100200024 target assembly. 3259100200025 (ERR-12) 0.1% correction for neutron scattering in 3259100200026 sample. 3259100200027 (ERR-13,0.1,3.2) error due to neutron energy dispersion3259100200028 COVARIANCE The relative covariance matrix is as follows: 3259100200029 1 2 3 4 5 6 7 8 En(MeV) 3259100200030 1 1.00 13.60 3259100200031 2 0.78 1.00 13.74 3259100200032 3 0.87 0.76 1.00 14.60 3259100200033 4 0.90 0.78 0.88 1.00 14.72 3259100200034 5 0.76 0.66 0.75 0.77 1.00 14.81 3259100200035 6 0.75 0.65 0.74 0.76 0.64 1.00 15.37 3259100200036 7 0.61 0.53 0.60 0.61 0.53 0.55 1.00 17.04 3259100200037 8 0.61 0.53 0.60 0.62 0.53 0.55 0.62 1.00 17.77 3259100200038 HISTORY (19970421U) Keyword PART-DET deleted 3259100200039 ENDBIB 37 0 3259100200040 COMMON 6 3 3259100200041 ERR-2 ERR-3 ERR-5 ERR-6 ERR-11 ERR-12 3259100200042 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3259100200043 3.8 1. 1. 0.1 0.1 0.1 3259100200044 ENDCOMMON 3 0 3259100200045 DATA 4 8 3259100200046 EN EN-ERR DATA ERR-T 3259100200047 MEV MEV MB MB 3259100200048 13.60 0.30 55.3 2.6 3259100200049 13.74 0.11 51.7 2.7 3259100200050 14.60 0.22 48.3 2.4 3259100200051 14.72 0.26 45.7 2.2 3259100200052 14.81 0.30 47.8 2.4 3259100200053 15.37 0.44 44.2 2.2 3259100200054 17.04 0.17 35.5 2.2 3259100200055 17.77 0.18 31.4 2.0 3259100200056 ENDDATA 10 0 3259100200057 ENDSUBENT 56 0 3259100299999 SUBENT 32591003 20100328 31473259100300001 BIB 5 35 3259100300002 REACTION (27-CO-59(N,A)25-MN-56,,SIG) 3259100300003 DECAY-DATA (25-MN-56,2.578HR,DG,847.,0.989) 3259100300004 ERR-ANALYS (ERR-T) Main error sources as follows: 3259100300005 (ERR-S,0.6,36.) statistical of gamma-ray from 3259100300006 residual nuclei. 3259100300007 (DATA-ERR,0.5,2.8) statist. of gamma-ray from monitor 3259100300008 (ERR-2) 1.% detector efficiency for gamma-ray from 3259100300009 residual nuclei. 3259100300010 (ERR-3) 1.0% detector efficiency for gamma-ray from 3259100300011 monitor 3259100300012 (MONIT-ERR,0.4,2.1) uncertainty in monitor reaction 3259100300013 (ERR-5) 1.0% correction for residual nuclei gamm 3259100300014 ray self-absorption in sample. 3259100300015 (ERR-6) 0.1% correction for Na-24 gamma-ray self 3259100300016 absorption in sample. 3259100300017 (ERR-7,0.3,0.6) correction for neutron flux 3259100300018 fluctuation of residual nuclei. 3259100300019 (ERR-8,0.15,0.3) correction for neutron flux 3259100300020 fluctuation of Na-24. 3259100300021 (ERR-9,0.0033,0.006) nuclides number in sample. 3259100300022 (ERR-10,0.012,0.015) nuclides number in Al-27 monitor 3259100300023 (ERR-11) 0.1% correction for neutron scattering in 3259100300024 target assembly. 3259100300025 (ERR-12) 0.1% correction for neutron scattering in 3259100300026 sample. 3259100300027 (ERR-13,2.3,6.0) error due to neutron energy dispersion3259100300028 COVARIANCE The relative covariance matrix are as follows: 3259100300029 1 2 3 4 5 6 En(MeV) 3259100300030 1 1.00 13.74 3259100300031 2 0.56 1.00 14.60 3259100300032 3 0.50 0.80 1.00 14.72 3259100300033 4 0.24 0.50 0.48 1.00 16.42 3259100300034 5 0.20 0.39 0.36 0.67 1.00 17.04 3259100300035 6 0.11 0.22 0.23 0.43 0.51 1.00 17.77 3259100300036 HISTORY (19970421U) Keyword PART-DET deleted 3259100300037 ENDBIB 35 0 3259100300038 COMMON 6 3 3259100300039 ERR-2 ERR-3 ERR-5 ERR-6 ERR-11 ERR-12 3259100300040 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3259100300041 1. 1. 1. 0.1 0.1 0.1 3259100300042 ENDCOMMON 3 0 3259100300043 DATA 4 6 3259100300044 EN EN-ERR DATA ERR-T 3259100300045 MEV MEV MB MB 3259100300046 13.74 0.11 32.0 1.6 3259100300047 14.60 0.22 30.4 1.6 3259100300048 14.72 0.26 31.3 1.9 3259100300049 16.42 0.60 25.8 1.9 3259100300050 17.04 0.17 23.4 1.4 3259100300051 17.77 0.18 20.0 1.4 3259100300052 ENDDATA 8 0 3259100300053 ENDSUBENT 52 0 3259100399999 SUBENT 32591004 20100328 31473259100400001 BIB 5 38 3259100400002 REACTION (27-CO-59(N,2N)27-CO-58,,SIG) 3259100400003 DECAY-DATA (27-CO-58-G,70.916D,DG,811.,0.9945) 3259100400004 ERR-ANALYS (ERR-T) Main error sources as follows: 3259100400005 (ERR-S,0.1,1.5) statistical of gamma-ray from 3259100400006 residual nuclei. 3259100400007 (DATA-ERR,0.5,3.7) statist. of gamma-ray from monitor 3259100400008 (ERR-2) 1.% detector efficiency for gamma-ray from 3259100400009 residual nuclei. 3259100400010 (ERR-3) 1.0% detector efficiency for gamma-ray from 3259100400011 monitor 3259100400012 (MONIT-ERR,0.4,3.1) uncertainty in monitor reaction 3259100400013 (ERR-5) 1.0% correction for residual nuclei gamm 3259100400014 ray self-absorption in sample. 3259100400015 (ERR-6) 0.1% correction for Na-24 gamma-ray self 3259100400016 absorption in sample. 3259100400017 (ERR-7,0.05,0.07) correction for neutron flux 3259100400018 fluctuation of residual nuclei. 3259100400019 (ERR-8,0.1,0.3) correction for neutron flux 3259100400020 fluctuation of Na-24. 3259100400021 (ERR-9,0.0033,0.0075) nuclides number in sample. 3259100400022 (ERR-10,0.013,0.015) nuclides number in Al-27 monitor 3259100400023 (ERR-11) 0.15% correction for neutron scattering in 3259100400024 target assembly. 3259100400025 (ERR-12) 0.1% correction for neutron scattering in 3259100400026 sample. 3259100400027 (ERR-13,1.5,8.0) error due to neutron energy dispersion3259100400028 COVARIANCE The relative covariance matrix are as follows: 3259100400029 1 2 3 4 5 6 7 8 9 En(MeV 3259100400030 1 1.00 12.84 3259100400031 2 0.32 1.00 13.60 3259100400032 3 0.28 0.72 1.00 13.74 3259100400033 4 0.27 0.73 0.69 1.00 14.60 3259100400034 5 0.26 0.58 0.65 0.93 1.00 14.72 3259100400035 6 0.24 0.67 0.64 0.93 0.93 1.00 14.81 3259100400036 7 0.22 0.56 0.54 0.79 0.86 0.83 1.00 15.37 3259100400037 8 0.13 0.32 0.31 0.51 0.77 0.63 0.62 1.00 17.04 3259100400038 9 0.10 0.21 0.20 0.36 0.37 0.39 0.47 0.74 1.00 17.77 3259100400039 HISTORY (19970421U) Keyword PART-DET deleted 3259100400040 ENDBIB 38 0 3259100400041 COMMON 6 3 3259100400042 ERR-2 ERR-3 ERR-5 ERR-6 ERR-11 ERR-12 3259100400043 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3259100400044 1. 1. 1.0 0.1 0.15 0.1 3259100400045 ENDCOMMON 3 0 3259100400046 DATA 4 9 3259100400047 EN EN-ERR DATA ERR-T 3259100400048 MEV MEV MB MB 3259100400049 12.84 0.34 490.0 47. 3259100400050 13.60 0.30 640.0 27. 3259100400051 13.74 0.11 649.0 27. 3259100400052 14.60 0.22 761.0 37. 3259100400053 14.72 0.26 764.0 43. 3259100400054 14.81 0.30 816.0 52. 3259100400055 15.37 0.44 804.0 53. 3259100400056 17.04 0.17 913.0 50. 3259100400057 17.77 0.18 918.0 63. 3259100400058 ENDDATA 11 0 3259100400059 ENDSUBENT 58 0 3259100499999 ENDENTRY 4 0 3259199999999