ENTRY 22864 20151003 22452286400000001 SUBENT 22864001 20151003 22452286400100001 BIB 10 25 2286400100002 TITLE Precise measurement of the Al-27(n,2n)Al-26-g 2286400100003 excitation function near threshold and its relevance 2286400100004 for fusion-plasma technology. 2286400100005 AUTHOR (A.Wallner,S.V.Chuvaev,A.A.Filatenkov,Y.Ikeda, 2286400100006 W.Kutschera,G.Mertens,A.Priller,W.Rochow,P.Steier, 2286400100007 H.Vonach) 2286400100008 INSTITUTE (2AUSIRK) 2286400100009 (4RUSRI) 2286400100010 (2JPNJAE) 2286400100011 (2GERTUE) 2286400100012 REFERENCE (J,EPJ/A,17,285,2003) Main Reference. 2286400100013 (C,2004SANTA,1,621,200409) Graphs 2286400100014 FACILITY (SPECM,2AUSIRK) Accelerator mass spectrometry at VERA. 2286400100015 METHOD (AMS,STTA) 2286400100016 INC-SOURCE (D-T) A deuterium-tritium 2286400100017 COMMENT *By authors*.The amount of Al-26 nuclei formed in all 2286400100018 irradiations was determined via accelerator mass 2286400100019 spectrometry with the Vienna environmental research 2286400100020 accelerator. 2286400100021 STATUS (TABLE) From table of EPJ/A,17,285,2003 2286400100022 HISTORY (20041208C) 2286400100023 (20070628A) 2nd Reference was added. M.M. 2286400100024 (20151003A) SD: FACILITY code corrected in Subent 003.22286400100025 ERR-ANALYS moved to Subents 002 - 003. ADD-RES deleted 2286400100026 (it is conclusion, not additional results). 2286400100027 ENDBIB 25 0 2286400100028 NOCOMMON 0 0 2286400100029 ENDSUBENT 28 0 2286400199999 SUBENT 22864002 20151003 22452286400200001 BIB 8 37 2286400200002 REACTION (13-AL-27(N,2N)13-AL-26-G,,SIG) 2286400200003 Final results as determined from Al-26/Al-27 ratios 2286400200004 and neutron fluences. 2286400200005 SAMPLE Pure Al-metal samples, 99.999% enrichment, 1-mm 2286400200006 thickness and Nb-foil of 0.125-mm for the neutron 2286400200007 fluence determination, were used. 2286400200008 MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) Can be used for an 2286400200009 energy standard. 2286400200010 FACILITY (CCW,2AUSIRK) The Cockcroft-Walton type neutron 2286400200011 generator of the Radium Institute in Vienna. 2286400200012 Deuterons with an energy 230-KeV were produced. 2286400200013 INC-SPECT The neutron fluence: 1.4 x 10**14 n/cm2 2286400200014 DETECTOR (HPGE) For activity Nb-samples. 2286400200015 (NAICR) 2286400200016 ERR-ANALYS (ERR-T) The total error consists of systematic and 2286400200017 random contributions: 2286400200018 (ERR-1,,2.7) the uncertainty of the neutron fluence 2286400200019 amounts to less or equal 2.7%. 2286400200020 (ERR-2) the uncertainty of the Al-26/Al-27 standard 2286400200021 (DATA-ERR1,1.5,10.5) the uncertainty from averaging of 2286400200022 the individual results over the whole sample area as 2286400200023 well as statistical errors. The latter dominate the low2286400200024 isotope ratios, whereas systematic errors affect the 2286400200025 higher cross-sections. 2286400200026 (DATA-ERR2,2.5,50.) The neutron energy in the near- 2286400200027 threshold region was assumed to be known to better than2286400200028 40-KeV. This leads to an additional uncertainty of 2286400200029 0.8-mb for a neutron energy of 13.8-MeV. It corresponds2286400200030 to an error of about 50% at 13.8-MeV and about 25% at 2286400200031 13.9-MeV and reflects the steeply raising shape of the 2286400200032 excitation function near threshold. For the higher- 2286400200033 energy region, a 20-KeV uncertainty was assumed, which 2286400200034 corresponds to absolute uncertainties of 0.6-mb, i.e. 2286400200035 10% at 14-MeV neutron energy and 2.4% for 14.8-MeV. 2286400200036 (EN-ERR).The error is reported by authors in table. 2286400200037 HISTORY (20151003A) SD: ERR-ANALYS added, DATA-ERR -> ERR-T; 2286400200038 COMMON section added. 2286400200039 ENDBIB 37 0 2286400200040 COMMON 1 3 2286400200041 ERR-2 2286400200042 PER-CENT 2286400200043 3.5 2286400200044 ENDCOMMON 3 0 2286400200045 DATA 4 14 2286400200046 EN EN-ERR DATA ERR-T 2286400200047 MEV MEV MB MB 2286400200048 13.67 0.04 0.03 0.04 2286400200049 13.71 0.04 0.2 0.06 2286400200050 13.77 0.04 0.8 0.1 2286400200051 13.85 0.04 2.5 0.3 2286400200052 13.89 0.04 3.3 0.4 2286400200053 13.98 0.03 5.4 0.4 2286400200054 14.09 0.02 7.8 0.5 2286400200055 14.15 0.02 9.8 0.7 2286400200056 14.28 0.02 13. 0.9 2286400200057 14.41 0.02 17.3 0.9 2286400200058 14.51 0.02 20. 1.3 2286400200059 14.61 0.02 23.5 1.3 2286400200060 14.73 0.02 27.1 1.5 2286400200061 14.83 0.02 30.8 1.6 2286400200062 ENDDATA 16 0 2286400200063 ENDSUBENT 62 0 2286400299999 SUBENT 22864003 20151003 22452286400300001 BIB 8 39 2286400300002 REACTION (13-AL-27(N,2N)13-AL-26-G,,SIG) 2286400300003 Final results as determined from Al-26/Al-27 ratios 2286400300004 and neutron fluences. 2286400300005 SAMPLE Individual Al-samples, 14-mm in diameter and 1-mm 2286400300006 thickness, were used. Nb-samples were used for the 2286400300007 fluence determination. Stacks of samples in the order 2286400300008 Nb-Al-Nb-Al-Nb were used. 2286400300009 MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) Can be used for an 2286400300010 energy standard. 2286400300011 FACILITY (CCW,4RUSRI) Neutron generator NG-400 of the Khlopin 2286400300012 Radium Institute. 2286400300013 Deuterons with an energy 300-KeV were produced. 2286400300014 INC-SPECT The neutron fluence: 1.5 x 10**14 n/cm2 2286400300015 DETECTOR (HPGE) For activity Nb-samples. 2286400300016 (NAICR) 2286400300017 ERR-ANALYS (ERR-T) The total error consists of systematic and 2286400300018 random contributions: 2286400300019 (ERR-2) the uncertainty of the Al-26/Al-27 standard 2286400300020 (DATA-ERR1,1.5,10.5) the uncertainty from averaging of 2286400300021 the individual results over the whole sample area as 2286400300022 well as statistical errors. The latter dominate the low2286400300023 isotope ratios, whereas systematic errors affect the 2286400300024 higher cross-sections. 2286400300025 No other information about sources of uncertainty, 2286400300026 except comment in the text of EPJ/A,17,285,2003: 2286400300027 Since the results from the three neutron irradiations 2286400300028 (Vienna, St. Petersburg and Tokai-mura) for 14 MeV 2286400300029 neutrons agree very well with each other, one can 2286400300030 safely assume that systematic errors in the neutron 2286400300031 irradiation have been largely eliminated. 2286400300032 The absolute values of the cross-sections are believed 2286400300033 to be known to about 5-8% in the energy region above 2286400300034 14 MeV. The uncertainty items mainly from systematic 2286400300035 errors. Overall, a very consistent set of cross-section2286400300036 data was obtained from the samples irradiated under 2286400300037 these different conditions. 2286400300038 (EN-ERR).The error is reported by authors in table. 2286400300039 HISTORY (20151002A) SD: FACILITY code corrected (REAC -> CCW). 2286400300040 ERR-ANALYS added,DATA-ERR -> ERR-T;COMMON section added2286400300041 ENDBIB 39 0 2286400300042 COMMON 1 3 2286400300043 ERR-2 2286400300044 PER-CENT 2286400300045 3.5 2286400300046 ENDCOMMON 3 0 2286400300047 DATA 4 10 2286400300048 EN EN-ERR DATA ERR-T 2286400300049 MEV MEV MB MB 2286400300050 13.68 0.05 0.15 0.1 2286400300051 13.74 0.04 0.52 0.1 2286400300052 13.74 0.04 0.58 0.1 2286400300053 13.87 0.03 3.1 0.4 2286400300054 14.07 0.02 6.7 0.5 2286400300055 14.29 0.02 12.5 0.8 2286400300056 14.48 0.03 18.5 1.3 2286400300057 14.7 0.04 24.2 1.8 2286400300058 14.7 0.04 25.3 1.3 2286400300059 14.84 0.06 30.6 1.8 2286400300060 ENDDATA 12 0 2286400300061 ENDSUBENT 60 0 2286400399999 SUBENT 22864004 20151003 22452286400400001 BIB 10 40 2286400400002 REACTION (13-AL-27(N,2N)13-AL-26-G,,SIG) 2286400400003 Final results as determined from Al-26/Al-27 ratios 2286400400004 and neutron fluences. 2286400400005 SAMPLE Sample arrangements was 5*Al-Nb. 2286400400006 MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) Can be used for an 2286400400007 energy standard. 2286400400008 FACILITY (REAC,2JPNJAE) The fusion neutrons source of the JAERI 2286400400009 in Tokai-Mura. 2286400400010 Deuterons with an energy 400-keV were produced. 2286400400011 DETECTOR (HPGE) For activity Nb-samples. 2286400400012 (NAICR) 2286400400013 INC-SPECT The high neutron fluence: 5. x 10**16 n/cm2 2286400400014 ANALYSIS (DECAY) The 26Al activity determined from a decay 2286400400015 measurement, and compared it with an independent 26Al 2286400400016 determination through AMS 2286400400017 REL-REF (M,,A.Wallner+,J,NIM/B,172,382,2000) 2286400400018 ERR-ANALYS (ERR-T) The total error consists of systematic and 2286400400019 random contributions: 2286400400020 (ERR-2) the uncertainty of the Al-26/Al-27 standard 2286400400021 (DATA-ERR1,1.5,10.5) the uncertainty from averaging of 2286400400022 the individual results over the whole sample area as 2286400400023 well as statistical errors. The latter dominate the low2286400400024 isotope ratios, whereas systematic errors affect the 2286400400025 higher cross-sections. 2286400400026 No other information about sources of uncertainty, 2286400400027 except comment in the text of EPJ/A,17,285,2003: 2286400400028 Since the results from the three neutron irradiations 2286400400029 (Vienna, St. Petersburg and Tokai-mura) for 14 MeV 2286400400030 neutrons agree very well with each other, one can 2286400400031 safely assume that systematic errors in the neutron 2286400400032 irradiation have been largely eliminated. 2286400400033 The absolute values of the cross-sections are believed 2286400400034 to be known to about 5-8% in the energy region above 2286400400035 14 MeV. The uncertainty items mainly from systematic 2286400400036 errors. Overall, a very consistent set of cross-section2286400400037 data was obtained from the samples irradiated under 2286400400038 these different conditions. 2286400400039 (EN-ERR).The error is reported by authors in table. 2286400400040 HISTORY (20151003A) SD: ERR-ANALYS added, DATA-ERR -> ERR-T; 2286400400041 ANALYSIS, COMMON section added. 2286400400042 ENDBIB 40 0 2286400400043 COMMON 1 3 2286400400044 ERR-2 2286400400045 PER-CENT 2286400400046 5.0 2286400400047 ENDCOMMON 3 0 2286400400048 DATA 4 1 2286400400049 EN EN-ERR DATA ERR-T 2286400400050 MEV MEV MB MB 2286400400051 14.8 0.05 29. 2. 2286400400052 ENDDATA 3 0 2286400400053 ENDSUBENT 52 0 2286400499999 SUBENT 22864005 20151003 22452286400500001 BIB 8 26 2286400500002 REACTION (13-AL-27(N,2N)13-AL-26-G,,SIG) 2286400500003 Final results as determined from Al-26/Al-27 ratios 2286400500004 and neutron fluences. 2286400500005 SAMPLE Al-samples, 1-cm in diameter and 1-mm thickness, were 2286400500006 used. The sample arrangement consisted of a stack of 2286400500007 foils in the succession of Ni-Al-Ni-Al-Ni, Ni-foils 2286400500008 each 0.125-mm thick. 2286400500009 MONITOR (28-NI-58(N,X)27-CO-57,,SIG) For the determination of 2286400500010 the neutron fluence. 2286400500011 FACILITY (VDG,2GERTUE) A single-ended 3-MV Van de Graaff 2286400500012 accelerator. 2286400500013 Deuterons with an energy of 1.2-MeV and 2.6-MeV were 2286400500014 produced. 2286400500015 INC-SPECT The neutron fluence: 1.2 x 10**12 n/cm2 2286400500016 DETECTOR (NAICR) 2286400500017 ERR-ANALYS (ERR-T) The main contributions to the uncertainty 2286400500018 of the cross-section values are: 2286400500019 (ERR-1) the uncertainty of the neutron fluence amounts 2286400500020 (ERR-2) the uncertainty from the AMS measurements 2286400500021 (isotope ratios in the order of 10**(-13)) 2286400500022 The total error of the cross-section data amounts to 7%2286400500023 (EN-ERR) The uncertainty of the neutron energy is 2286400500024 negligible due to the nearly energy-independent shape 2286400500025 of the excitation function in this energy region 2286400500026 HISTORY (20151003A) SD: ERR-ANALYS added, DATA-ERR -> ERR-T; 2286400500027 COMMON section added. 2286400500028 ENDBIB 26 0 2286400500029 COMMON 2 3 2286400500030 ERR-1 ERR-2 2286400500031 PER-CENT PER-CENT 2286400500032 4.7 5.0 2286400500033 ENDCOMMON 3 0 2286400500034 DATA 4 4 2286400500035 EN EN-ERR DATA ERR-T 2286400500036 MEV MEV MB MB 2286400500037 17. 0.1 83. 6. 2286400500038 17. 0.1 85. 6. 2286400500039 19. 0.1 96. 7. 2286400500040 19. 0.1 105. 8. 2286400500041 ENDDATA 6 0 2286400500042 ENDSUBENT 41 0 2286400599999 ENDENTRY 5 0 2286499999999