ENTRY 14497 20180503 14411449700000001 SUBENT 14497001 20180503 14411449700100001 BIB 13 53 1449700100002 TITLE 12C(n,2n) 11C cross section from threshold to 26.5 MeV 1449700100003 AUTHOR (M.Yuly,T.Eckert,G.Hartshaw,S.J.Padalino,D.N.Polsin, 1449700100004 M.Russ,A.T.Simone,C.R.Brune,T.N.Massey,C.E.Parker, 1449700100005 R.Fitzgerald,T.C.Sangster,S.P.Regan) 1449700100006 INSTITUTE (1USAOHO,1USANIS,1USAROC) 1449700100007 (1USAUSA) Hougheton College, Houghton, New York 1449700100008 (1USAUSA) State University of New York, Geneseo, New 1449700100009 York 1449700100010 REFERENCE (J,PR/C,97,024613,2018) 1449700100011 FACILITY (VDGT,1USAOHO) Experiment was performed using the 4.5 1449700100012 MV Tandem Pelletron electrostatic accelerator at Ohio 1449700100013 University. 1449700100014 SAMPLE Two targets were used simultaneously a graphite and a 1449700100015 CH2 plastic target. 1449700100016 DETECTOR (TELES,SI,SILI) A proton telescope consisting of a 1449700100017 300 mu-m thick, 150 mm2 ion implanted silicon dE 1449700100018 detector and a 5000 mu-m thick, 200 mm2 drifted- 1449700100019 lithium silicon E detector was used to detect recoil 1449700100020 protons from CH2 target to determine the neutron flux. 1449700100021 (NAICR) Three pairs of 7.62-cm diameter by 7.62-cm 1449700100022 thick NaI detectors were used to measure positron 1449700100023 annihilation gamma rays from 11C decays. Pairs of 1449700100024 detectors and the graphite targets were held with 1449700100025 their axes aligned inside almost equal diameter 1449700100026 acrylic tubes. CH2 target, graphite target and 1449700100027 graphite shields were mesured simultaneously after 1449700100028 irradiation. 1449700100029 METHOD (ACTIV) The polyethylene target also acted 1449700100030 simultaneously as the converter for the recoil proton 1449700100031 telescope. Special care was taken for exact geometrical1449700100032 alignement of all components, beam, Ti neutron 1449700100033 producing target, CH2 and graphite targets and 1449700100034 proton telescope. 1449700100035 INC-SOURCE (D-T) Deuterons were accelerated to energies between 1449700100036 3.1 and 9.1 MeV and allowed to strike a 472.86 GBq 1449700100037 tritium target. Deuteron beam currents were typically 1449700100038 between 0.8 and 1.0 mu-A. The tritium was deposited 1449700100039 as titanium tritide on a 49-mm diameter 1-mm thick 1449700100040 OFHC copper substrate at a density of about 2000 1449700100041 mu-g/cm2 over a circular active area of 30-mm diameter.1449700100042 ANALYSIS Cross section was determined from the analysis of the 1449700100043 11B growth curves from decay of 11C for coincidence 1449700100044 and singles measurements. 1449700100045 At the energy of 24.7 MeV two independent measurements 1449700100046 were made with slightly different results. Both data 1449700100047 at 24.69 MeV(graphite terget) and 24.74 (polyethylene 1449700100048 target) are compiled. 1449700100049 DECAY-DATA (6-C-11,20.364MIN,AR) 1449700100050 ERR-ANALYS (ERR-1) Syst. uncertainty in NaI detector efficiency 1449700100051 (ERR-2) Syst. uncertainty in decay constant factor 1449700100052 (L/(1-exp(-Lt) , L=lambda 1449700100053 (ERR-T) Total uncertainty 1449700100054 HISTORY (20180503C) Compiled by S.H. 1449700100055 ENDBIB 53 0 1449700100056 COMMON 2 3 1449700100057 ERR-1 ERR-2 1449700100058 PER-CENT PER-CENT 1449700100059 5.5 0.6 1449700100060 ENDCOMMON 3 0 1449700100061 ENDSUBENT 60 0 1449700199999 SUBENT 14497002 20180503 14411449700200001 BIB 5 14 1449700200002 REACTION (6-C-12(N,2N)6-C-11,,SIG) 1449700200003 STATUS (TABLE) Data taken from tab. 4 of the reference 1449700200004 SAMPLE High purity graphite target with dimensions 1449700200005 Outer diameter 7.62 cm 1449700200006 Inner diameter 1.746 cm 1449700200007 Thickness 0.89 cm 1449700200008 mass density of 1.842+-0.012 g/cm2 1449700200009 with its upstream face located 14.4 cm from the 1449700200010 tritium target 1449700200011 ERR-ANALYS (ERR-S,0.3,0.9) Statistical uncertainty in number of 1449700200012 of coincidence Counts 1449700200013 (ERR-3) Systematic uncertainty in 12C areal density 1449700200014 (ERR-4) Systematic uncertainty in neutron flux 1449700200015 ANALYSIS Cross section determined from coincidence counts 1449700200016 ENDBIB 14 0 1449700200017 COMMON 2 3 1449700200018 ERR-3 ERR-4 1449700200019 PER-CENT PER-CENT 1449700200020 1.9 6.9 1449700200021 ENDCOMMON 3 0 1449700200022 DATA 3 13 1449700200023 EN DATA ERR-T 1449700200024 MEV MB MB 1449700200025 20.06 0.00 0.00 1449700200026 20.67 0.08 0.01 1449700200027 21.27 0.78 0.32 1449700200028 21.79 2.69 0.43 1449700200029 22.35 4.37 0.57 1449700200030 22.92 6.76 0.77 1449700200031 23.51 8.19 0.92 1449700200032 24.11 8.89 1.01 1449700200033 24.69 12.34 1.31 1449700200034 24.69 12.19 1.30 1449700200035 25.25 13.45 1.44 1449700200036 25.77 15.91 1.67 1449700200037 26.25 18.16 1.89 1449700200038 ENDDATA 15 0 1449700200039 ENDSUBENT 38 0 1449700299999 SUBENT 14497003 20180503 14411449700300001 BIB 5 14 1449700300002 REACTION (6-C-12(N,2N)6-C-11,,SIG) 1449700300003 STATUS (TABLE) Data taken from tab. 4 of the reference 1449700300004 SAMPLE High purity graphite target with dimensions 1449700300005 Outer diameter 7.62 cm 1449700300006 Inner diameter 1.746 cm 1449700300007 Thickness 0.89 cm 1449700300008 mass density of 1.842+-0.012 g/cm2 1449700300009 with its upstream face located 14.4 cm from the 1449700300010 tritium target 1449700300011 ERR-ANALYS (ERR-S,0.2,1.0) Statistical uncertainty in number of 1449700300012 counts from NaI1 detector 1449700300013 (ERR-3) Systematic uncertainty in 12C areal density 1449700300014 (ERR-4) Systematic uncertainty in neutron flux 1449700300015 ANALYSIS Cross section determined from NaI1 singles counts 1449700300016 ENDBIB 14 0 1449700300017 COMMON 2 3 1449700300018 ERR-3 ERR-4 1449700300019 PER-CENT PER-CENT 1449700300020 1.9 6.9 1449700300021 ENDCOMMON 3 0 1449700300022 DATA 3 13 1449700300023 EN DATA ERR-T 1449700300024 MEV MB MB 1449700300025 20.06 -0.05 0.01 1449700300026 20.67 0.07 0.01 1449700300027 21.27 0.75 0.31 1449700300028 21.79 4.03 0.51 1449700300029 22.35 4.23 0.56 1449700300030 22.92 6.56 0.76 1449700300031 23.51 7.72 0.88 1449700300032 24.11 8.53 0.98 1449700300033 24.69 11.62 1.26 1449700300034 24.69 9.66 1.11 1449700300035 25.25 12.62 1.37 1449700300036 25.77 13.86 1.51 1449700300037 26.25 16.80 1.78 1449700300038 ENDDATA 15 0 1449700300039 ENDSUBENT 38 0 1449700399999 SUBENT 14497004 20180503 14411449700400001 BIB 5 14 1449700400002 REACTION (6-C-12(N,2N)6-C-11,,SIG) 1449700400003 STATUS (TABLE) Data taken from tab. 4 of the reference 1449700400004 SAMPLE High purity graphite target with dimensions 1449700400005 Outer diameter 7.62 cm 1449700400006 Inner diameter 1.746 cm 1449700400007 Thickness 0.89 cm 1449700400008 mass density of 1.842+-0.012 g/cm2 1449700400009 with its upstream face located 14.4 cm from the 1449700400010 tritium target 1449700400011 ERR-ANALYS (ERR-S,0.2,1.0) Statistical uncertainty in number of 1449700400012 counts from NaI2 detector 1449700400013 (ERR-3) Systematic uncertainty in 12C areal density 1449700400014 (ERR-4) Systematic uncertainty in neutron flux 1449700400015 ANALYSIS Cross section determined from NaI2 singles counts 1449700400016 ENDBIB 14 0 1449700400017 COMMON 2 3 1449700400018 ERR-3 ERR-4 1449700400019 PER-CENT PER-CENT 1449700400020 1.9 6.9 1449700400021 ENDCOMMON 3 0 1449700400022 DATA 3 13 1449700400023 EN DATA ERR-T 1449700400024 MEV MB MB 1449700400025 20.06 0.02 0.01 1449700400026 20.67 0.10 0.01 1449700400027 21.27 0.70 0.31 1449700400028 21.79 3.78 0.49 1449700400029 22.35 3.96 0.54 1449700400030 22.92 6.12 0.73 1449700400031 23.51 7.25 0.85 1449700400032 24.11 7.83 0.93 1449700400033 24.69 11.17 1.22 1449700400034 24.69 9.04 1.06 1449700400035 25.25 11.81 1.31 1449700400036 25.77 13.05 1.44 1449700400037 26.25 16.07 1.72 1449700400038 ENDDATA 15 0 1449700400039 ENDSUBENT 38 0 1449700499999 SUBENT 14497005 20180503 14411449700500001 BIB 5 13 1449700500002 REACTION (6-C-12(N,2N)6-C-11,,SIG) 1449700500003 STATUS (TABLE) Data taken from tab. 4 of the reference 1449700500004 SAMPLE High-density polyethylene target with 1449700500005 diameter of 2.54 cm 1449700500006 thickness of 1.64mm 1449700500007 mass density of 0.957 +- 0.008 g/cm2 1449700500008 with its upstream face located 7.0 cm from the 1449700500009 tritium target 1449700500010 ERR-ANALYS (ERR-S,0.7,2.3) Statistical uncertainty in number of 1449700500011 of coincidence counts 1449700500012 (ERR-3) Systematic uncertainty in 12C areal density 1449700500013 (ERR-4) Systematic uncertainty in neutron flux 1449700500014 ANALYSIS Cross section determined from coincidence counts 1449700500015 ENDBIB 13 0 1449700500016 COMMON 2 3 1449700500017 ERR-3 ERR-4 1449700500018 PER-CENT PER-CENT 1449700500019 3.8 4.6 1449700500020 ENDCOMMON 3 0 1449700500021 DATA 3 13 1449700500022 EN DATA ERR-T 1449700500023 MEV MB MB 1449700500024 20.10 0.00 0.01 1449700500025 20.71 0.08 0.01 1449700500026 21.31 0.88 0.32 1449700500027 21.83 2.53 0.41 1449700500028 22.39 4.02 0.52 1449700500029 22.97 6.49 0.70 1449700500030 23.56 7.58 0.80 1449700500031 24.15 8.50 0.90 1449700500032 24.74 11.09 1.10 1449700500033 24.74 10.77 1.08 1449700500034 25.29 12.04 1.20 1449700500035 25.82 13.91 1.36 1449700500036 26.29 16.55 1.56 1449700500037 ENDDATA 15 0 1449700500038 ENDSUBENT 37 0 1449700599999 SUBENT 14497006 20180503 14411449700600001 BIB 5 13 1449700600002 REACTION (6-C-12(N,2N)6-C-11,,SIG) 1449700600003 STATUS (TABLE) Data taken from tab. 4 of the reference 1449700600004 SAMPLE High-density polyethylene target with 1449700600005 diameter of 2.54 cm 1449700600006 thickness of 1.64mm 1449700600007 mass density of 0.957 +- 0.008 g/cm2 1449700600008 with its upstream face located 7.0 cm from the 1449700600009 tritium target 1449700600010 ERR-ANALYS (ERR-S,1.0,9.5) Statistical uncertainty in number of 1449700600011 counts from NaI1 detector 1449700600012 (ERR-3) Systematic uncertainty in 12C areal density 1449700600013 (ERR-4) Systematic uncertainty in neutron flux 1449700600014 ANALYSIS Cross section determined from NaI1 singles counts 1449700600015 ENDBIB 13 0 1449700600016 COMMON 2 3 1449700600017 ERR-3 ERR-4 1449700600018 PER-CENT PER-CENT 1449700600019 3.8 4.6 1449700600020 ENDCOMMON 3 0 1449700600021 DATA 3 13 1449700600022 EN DATA ERR-T 1449700600023 MEV MB MB 1449700600024 20.10 -0.03 0.13 1449700600025 20.71 0.50 0.11 1449700600026 21.31 0.79 0.33 1449700600027 21.83 4.04 0.49 1449700600028 22.39 4.14 0.53 1449700600029 22.97 6.00 0.69 1449700600030 23.56 7.43 0.80 1449700600031 24.15 8.18 0.88 1449700600032 24.74 10.70 1.08 1449700600033 24.74 8.58 0.95 1449700600034 25.29 11.44 1.16 1449700600035 25.82 13.36 1.32 1449700600036 26.29 16.43 1.56 1449700600037 ENDDATA 15 0 1449700600038 ENDSUBENT 37 0 1449700699999 SUBENT 14497007 20180503 14411449700700001 BIB 5 13 1449700700002 REACTION (6-C-12(N,2N)6-C-11,,SIG) 1449700700003 STATUS (TABLE) Data taken from tab. 4 of the reference 1449700700004 SAMPLE High-density polyethylene target with 1449700700005 diameter of 2.54 cm 1449700700006 thickness of 1.64mm 1449700700007 mass density of 0.957 +- 0.008 g/cm2 1449700700008 with its upstream face located 7.0 cm from the 1449700700009 tritium target 1449700700010 ERR-ANALYS (ERR-S,1.0,5.5) Statistical uncertainty in number of 1449700700011 counts from NaI2 detector 1449700700012 (ERR-3) Systematic uncertainty in 12C areal density 1449700700013 (ERR-4) Systematic uncertainty in neutron flux 1449700700014 ANALYSIS Cross section determined from NaI2 singles counts 1449700700015 ENDBIB 13 0 1449700700016 COMMON 2 3 1449700700017 ERR-3 ERR-4 1449700700018 PER-CENT PER-CENT 1449700700019 3.8 4.6 1449700700020 ENDCOMMON 3 0 1449700700021 DATA 3 13 1449700700022 EN DATA ERR-T 1449700700023 MEV MB MB 1449700700024 20.10 -0.20 0.01 1449700700025 20.71 0.12 0.01 1449700700026 21.31 1.49 0.32 1449700700027 21.83 3.72 0.41 1449700700028 22.39 3.83 0.52 1449700700029 22.97 6.44 0.70 1449700700030 23.56 7.48 0.80 1449700700031 24.15 8.49 0.90 1449700700032 24.74 10.77 1.10 1449700700033 24.74 9.59 1.08 1449700700034 25.29 12.75 1.20 1449700700035 25.82 12.57 1.36 1449700700036 26.29 16.94 1.56 1449700700037 ENDDATA 15 0 1449700700038 ENDSUBENT 37 0 1449700799999 ENDENTRY 7 0 1449799999999