ENTRY 23101 20120120 Y0082310100000001 SUBENT 23101001 20120120 Y0082310100100001 BIB 13 96 2310100100002 REFERENCE (J,NIM/A,580,1400,2007) 2310100100003 AUTHOR (G.Loevestam, M.Hult, A.Fessler, T.Gamboni, J.Gasparro,2310100100004 R.Jaime, P.Lindahl, S.Oberstedt, H.Tagziria) 2310100100005 TITLE Measurement of neutron excitation functions using wide 2310100100006 energy neutron beams. 2310100100007 INSTITUTE (2ZZZGEL) G.Loevestam, M.Hult, A.Fessler, T.Gamboni, 2310100100008 J.Gasparro, R.Jaime, P.Lindahl, S.Oberstedt. 2310100100009 (2ZZZISP) H.Tagziria. 2310100100010 SAMPLE Technique disks of natural indium.Isototic abundances:2310100100011 In-113 - 4.29 % , In-115 - 95.7 % . Disks of 20 mm 2310100100012 diameter, 5 mm thickness. Distance between the 2310100100013 neutron-producing target and disk was 20 cm. 2310100100014 FACILITY (VDG,2ZZZGEL) IRMM Van de Graaff. 2310100100015 DETECTOR (LONGC) Laboratory stationary long counter -for neutron2310100100016 beam monitoring. 2310100100017 (SPEC) IRMM Bonner sphere neutron spectrometer (PTB-C 2310100100018 design, MAXED unfolding program) for incident neutron 2310100100019 spectra measurement. 2310100100020 (HPGE) Low background HPGe-detector (Ge-T2) for gamma 2310100100021 ray measurement. Detectors is of 20.% relative 2310100100022 efficiency, coaxial detector with ultra-pure aluminum 2310100100023 (Kryal) end-cap and entrance window of 1.5mm thick. 2310100100024 Active volume of Ge-crystal 71.3 cm**3, crystal 2310100100025 diameter 59 mm. Calibrated experimentally by point 2310100100026 sources at different distances from detector, 2310100100027 average discrepancy of measured activity < 1.5 %. 2310100100028 INC-SOURCE (P-T) H-3(p,n) to produce neutrons in 0.5-2.8 MeV 2310100100029 energy range. Ti-H-3 target of 2.075 mg/cm**2. 2310100100030 H-3 to Ti ratio was calculated to be 1.22 at the time 2310100100031 for irradiation. Neutron spectrum was measured at 2310100100032 deuteron energy of 2.90 MeV, giving a peak neutron 2310100100033 energy of 6.0 MeV. 2310100100034 Neutron spectrum was measured at proton energy of 2310100100035 3.32 MeV, giving a peak neutron energy of 2.5 MeV. 2310100100036 (D-D) H-2(d,n) to produce neutrons in 4.0 - 5.5 MeV 2310100100037 energy range. Solid Ti-H-2 target of 2.065 mg/cm**2 . 2310100100038 H-2/Ti ratio was 1.48 . 2310100100039 The given neutron energies are for 0 degrees relative 2310100100040 the ion beam.Since the target(the disk) to Be activated2310100100041 is scanned in front of the neutron producing target 2310100100042 the disk is irradiated by a continuum of neutron 2310100100043 energies from 0-5.5 MeV. 2310100100044 Simulated and measured spectra agree well in the higher2310100100045 energy region, but considerable difference is noticed 2310100100046 in the lower energy part ( Fig.5 of NIM/A,580,1400). 2310100100047 METHOD (ACTIV) 10 irradiations: 2310100100048 En F(0deg) F(80deg) Irrad.time A(In113) A(In115) 2310100100049 (MeV) (10**3n/cm**2/sec) (sec) (10**-21 Bq/atoms) 2310100100050 0.500 753 292 10.498 0.11+-0.012310100100051 1.000 724 397 12.885 4.5+-0.3 4.1+-0.2 2310100100052 1.500 630 262 56.249 18.7+-0.3 24.6+-1.1 2310100100053 1.745 774 267 9391. 21.5+-0.3 14.9+-0.7 2310100100054 2.000 488 146 55.205 30.1+-0.3 36.4+-1.7 2310100100055 2.800 648 156 11.967 44.1+-0.4 29.8+-1.4 2310100100056 4.000 135 25 9840. 7.30+-0.14 4.02+-0.192310100100057 4.446 356 59 8115. 14.90+-0.18 8.5+-0.4 2310100100058 5.000 320 47 8660 12.44+-0.17 7.5+-0.3 2310100100059 5.500 405 54 58.184 21.1+-0.2 25.6+-1.2 2310100100060 En - neutron peak energy, 2310100100061 F - average neutron fluence rate, calculated by 2310100100062 Target code, at distance of 20 cm from neutron- 2310100100063 producing target, i.e at the front side of sample,2310100100064 A(In113) - measured activity of In-113-m, 2310100100065 A(In115) - measured activity of In-115-m 2310100100066 ( with standard uncertainties, calculated following 2310100100067 ISO/BIPM Guide to Expression of Uncertainty in 2310100100068 Measurement, ISBN:92-67-10188-9). 2310100100069 Simulated total neutron fluence spectra are given on 2310100100070 Fig.3 of J,NIM/A,580,1400. 2310100100071 CORRECTION No corrections for multiple scattered neutrons in the 2310100100072 disk material . 2310100100073 No corrections for difference in solid angle due to 2310100100074 the finite thickness of the disks. 2310100100075 ERR-ANALYS (ERR-6,,0.5) Uncertainty of geometrical characteristics2310100100076 of sample disks < 0.5 %. 2310100100077 (ERR-1) Uncertainty of sample mass determination. 2310100100078 Uncertainty of counting statistics around or less 1%. 2310100100079 (ERR-2) Uncertainty in detector efficiency estimation. 2310100100080 (ERR-3) Uncertainty of default curve. 2310100100081 (ERR-4) Uncertainty of calculations of neutron fluence 2310100100082 fields, based on measurement and calculations. 2310100100083 (ERR-7,,1.5) Sum of uncertainties, including the 2310100100084 measurement of distance between neutron-producing 2310100100085 target and samples,the weighting of samples, the 2310100100086 measurement of sample dimensions and the normalization 2310100100087 to ion beam current up to 1.5%. 2310100100088 (ERR-T) Total uncertainty. 2310100100089 The MAXED code comes in a software package called UMG 2310100100090 (Unfolding using MAXED and GRAVEL) which also 2310100100091 facilitates uncertainty calculations using output data2310100100092 from the MAXED code (author's comment). 2310100100093 STATUS (TABLE) Request for the data was sent 07.09.2009 to 2310100100094 Goeran Loevestam. Data received from Goeran Loevestam 2310100100095 08.09.2009 . 2310100100096 (APRVD) Goeran Loevestam, 14.09.2009. 2310100100097 HISTORY (20090907C) M.M. 2310100100098 ENDBIB 96 0 2310100100099 COMMON 4 3 2310100100100 ERR-1 ERR-2 ERR-3 ERR-4 2310100100101 PER-CENT PER-CENT PER-CENT PER-CENT 2310100100102 0.05 3. 10. 5. 2310100100103 ENDCOMMON 3 0 2310100100104 ENDSUBENT 103 0 2310100199999 SUBENT 23101002 20120120 Y0082310100200001 BIB 7 22 2310100200002 REACTION (49-IN-115(N,INL)49-IN-115-M,,SIG) 2310100200003 DECAY-DATA (49-IN-115-M,4.486HR,DG,336.) 2310100200004 REL-REF (R,,J.Blachot,J,NDS,104,967,2005) Nuclear data used. 2310100200005 #doi:10.1016/j.nds.2005.03.003 2310100200006 ANALYSIS (UNFLD)Cross-section data were unfolded to 140 channels2310100200007 covering the neutron energy region 0 - 5.6 MeV. 2310100200008 IRDF-2002 data were used as default curve in unfolding.2310100200009 Normalization was done to the integrated cross-section,2310100200010 sig-115def, calculated for up to 5.6 MeV neutrons to 2310100200011 1.380 b from default curve. 2310100200012 The MAXED unfolding routine allows for uncertainty 2310100200013 propagation. 2310100200014 ERR-ANALYS (ERR-5) Uncertainty of emission probability for 2310100200015 336 keV gamma line. 2310100200016 En,MeV Total uncertainty, % 2310100200017 < 0.5 10.0 - 25.5 2310100200018 0.5-1.0 6.6 - 11.6 2310100200019 > 1.0 5.0 - 7.2 2310100200020 STATUS (TABLE) Data received from Goeran Loevestam 08.09.2009.2310100200021 Data are presented on Fig. 6, bottom, of 2310100200022 J,NIM/A,580,1400. 2310100200023 HISTORY (20120120A) NDS(VZ): REL-REF: ND/B->NDS 2310100200024 ENDBIB 22 0 2310100200025 COMMON 1 3 2310100200026 ERR-5 2310100200027 PER-CENT 2310100200028 4.8 2310100200029 ENDCOMMON 3 0 2310100200030 DATA 3 134 2310100200031 EN DATA ERR-T 2310100200032 MEV MB PER-CENT 2310100200033 0.280 0.000 24.8 2310100200034 0.320 0.076 25.6 2310100200035 0.360 0.298 23.8 2310100200036 0.400 0.571 20.7 2310100200037 0.440 0.892 18.0 2310100200038 0.480 1.430 16.1 2310100200039 0.520 2.309 11.7 2310100200040 0.560 3.670 9.5 2310100200041 0.600 5.749 7.6 2310100200042 0.640 9.451 6.6 2310100200043 0.680 14.000 7.1 2310100200044 0.720 18.010 7.3 2310100200045 0.760 22.490 7.1 2310100200046 0.800 27.760 7.1 2310100200047 0.840 33.790 7.4 2310100200048 0.880 39.570 8.0 2310100200049 0.920 46.980 7.6 2310100200050 0.960 55.830 7.0 2310100200051 1.000 65.180 6.6 2310100200052 1.040 74.750 6.0 2310100200053 1.080 84.670 5.6 2310100200054 1.120 96.670 5.7 2310100200055 1.160 105.700 5.8 2310100200056 1.200 114.900 6.0 2310100200057 1.240 123.700 6.2 2310100200058 1.280 133.400 6.3 2310100200059 1.320 142.700 6.1 2310100200060 1.360 153.500 6.8 2310100200061 1.400 167.700 7.0 2310100200062 1.440 178.200 6.8 2310100200063 1.480 187.100 6.5 2310100200064 1.520 195.400 6.3 2310100200065 1.560 204.100 5.9 2310100200066 1.600 209.900 6.1 2310100200067 1.640 222.300 6.9 2310100200068 1.680 233.700 7.1 2310100200069 1.720 241.300 6.8 2310100200070 1.760 249.200 6.1 2310100200071 1.800 255.400 6.0 2310100200072 1.840 259.300 5.9 2310100200073 1.880 272.200 6.3 2310100200074 1.920 289.800 6.8 2310100200075 1.960 293.900 6.4 2310100200076 2.000 296.700 6.0 2310100200077 2.040 296.700 5.6 2310100200078 2.080 290.500 5.0 2310100200079 2.120 291.600 5.0 2310100200080 2.160 300.000 5.0 2310100200081 2.200 307.500 5.0 2310100200082 2.240 314.100 5.1 2310100200083 2.280 321.900 5.3 2310100200084 2.320 327.700 5.1 2310100200085 2.360 333.500 5.2 2310100200086 2.400 339.200 5.4 2310100200087 2.440 342.900 5.2 2310100200088 2.480 347.900 5.1 2310100200089 2.520 351.100 5.4 2310100200090 2.560 354.800 5.3 2310100200091 2.600 358.900 5.5 2310100200092 2.640 362.900 5.5 2310100200093 2.680 367.100 5.7 2310100200094 2.720 375.800 6.1 2310100200095 2.760 374.000 6.1 2310100200096 2.800 363.400 5.6 2310100200097 2.840 350.900 5.4 2310100200098 2.880 332.300 4.9 2310100200099 2.920 329.400 5.0 2310100200100 2.960 327.300 5.0 2310100200101 3.000 326.600 5.1 2310100200102 3.040 325.000 5.2 2310100200103 3.080 323.600 5.1 2310100200104 3.120 322.400 5.1 2310100200105 3.160 321.500 5.1 2310100200106 3.200 321.700 5.2 2310100200107 3.240 321.000 5.3 2310100200108 3.280 320.300 5.1 2310100200109 3.320 319.800 5.3 2310100200110 3.360 320.100 5.3 2310100200111 3.400 320.100 5.3 2310100200112 3.440 318.600 5.2 2310100200113 3.480 317.400 5.2 2310100200114 3.520 316.100 5.4 2310100200115 3.560 314.800 5.3 2310100200116 3.600 313.300 5.5 2310100200117 3.640 311.500 5.6 2310100200118 3.680 311.100 5.5 2310100200119 3.720 310.000 5.5 2310100200120 3.760 310.000 5.5 2310100200121 3.800 309.000 5.5 2310100200122 3.840 309.000 5.5 2310100200123 3.880 309.000 5.5 2310100200124 3.920 309.000 5.5 2310100200125 3.960 309.200 5.6 2310100200126 4.000 309.400 5.6 2310100200127 4.040 309.800 5.4 2310100200128 4.080 310.300 5.6 2310100200129 4.120 311.000 5.5 2310100200130 4.160 311.900 5.4 2310100200131 4.200 314.100 5.8 2310100200132 4.240 315.000 5.7 2310100200133 4.280 317.000 5.7 2310100200134 4.320 319.000 5.6 2310100200135 4.360 320.100 5.7 2310100200136 4.400 320.200 5.7 2310100200137 4.440 321.400 5.4 2310100200138 4.480 321.700 5.5 2310100200139 4.520 323.000 5.3 2310100200140 4.560 323.400 5.4 2310100200141 4.600 324.800 5.2 2310100200142 4.640 325.400 5.3 2310100200143 4.680 326.800 5.1 2310100200144 4.720 329.100 5.2 2310100200145 4.760 331.600 5.3 2310100200146 4.800 336.600 5.5 2310100200147 4.840 337.800 5.6 2310100200148 4.880 338.500 5.5 2310100200149 4.920 339.300 5.7 2310100200150 4.960 338.900 5.6 2310100200151 5.000 339.500 5.4 2310100200152 5.040 339.000 5.3 2310100200153 5.080 339.100 5.3 2310100200154 5.120 339.100 5.3 2310100200155 5.160 337.600 5.2 2310100200156 5.200 334.500 5.2 2310100200157 5.240 337.100 5.4 2310100200158 5.280 340.700 5.5 2310100200159 5.320 348.200 5.8 2310100200160 5.360 352.800 5.9 2310100200161 5.400 352.100 6.0 2310100200162 5.440 349.800 5.9 2310100200163 5.480 347.200 5.8 2310100200164 5.520 345.300 5.6 2310100200165 5.560 341.500 5.4 2310100200166 5.600 336.700 5.3 2310100200167 ENDDATA 136 0 2310100200168 ENDSUBENT 167 0 2310100299999 SUBENT 23101003 20120120 Y0082310100300001 BIB 7 24 2310100300002 REACTION (49-IN-113(N,INL)49-IN-113-M,,SIG) 2310100300003 DECAY-DATA (49-IN-113-M,1.658HR) 2310100300004 REL-REF (R,,J.Blachot,J,NDS,104,791,2005) Nuclear data used. 2310100300005 #doi:10.1016/j.nds.2005.03.003 2310100300006 ANALYSIS (UNFLD)Cross-section data were unfolded to 140 channels2310100300007 covering the neutron energy region 0 - 5.6 MeV. 2310100300008 9 degrees polynomial fit to selected data points from 2310100300009 EXFOR were used as default curve in unfolding. 2310100300010 Normalization was done to the integrated cross-section,2310100300011 sig-113, calculated to 1.196 b, using the integrated 2310100300012 cross section for In-115, sig-115def, and corresponding2310100300013 integrated values for the unfolded excitation functions2310100300014 for In-115 and In-113, f-113 and f-115,respectively: 2310100300015 sig-113 = (f-113/f-115)*sig-115def. 2310100300016 The MAXED unfolding routine allows for uncertainty 2310100300017 propagation. 2310100300018 STATUS (TABLE) Data received from Goeran Loevestam 08.09.2009.2310100300019 Data are presented on Fig. 6, top of J,NIM/A,580,1400.2310100300020 (DEP,23101002) 2310100300021 ERR-ANALYS En,MeV Total uncertainty, % 2310100300022 < 0.5 10.0 - 12.4 2310100300023 0.5-1.0 7.6 - 9.2 2310100300024 > 1.0 5.0 - 6.2 2310100300025 HISTORY (20120120A) NDS(VZ): REL-REF: ND/B->NDS 2310100300026 ENDBIB 24 0 2310100300027 NOCOMMON 0 0 2310100300028 DATA 3 129 2310100300029 EN DATA ERR-T 2310100300030 MEV MB PER-CENT 2310100300031 0.480 0.000 12.4 2310100300032 0.520 1.377 8.5 2310100300033 0.560 3.616 8.2 2310100300034 0.600 5.943 7.8 2310100300035 0.640 8.302 7.7 2310100300036 0.680 10.820 7.7 2310100300037 0.720 13.350 7.9 2310100300038 0.760 15.600 7.7 2310100300039 0.800 17.840 8.1 2310100300040 0.840 19.860 8.4 2310100300041 0.880 21.280 9.3 2310100300042 0.920 25.110 8.4 2310100300043 0.960 30.190 7.6 2310100300044 1.000 35.940 7.1 2310100300045 1.040 42.850 6.2 2310100300046 1.080 51.430 5.5 2310100300047 1.120 65.180 5.3 2310100300048 1.160 71.910 5.3 2310100300049 1.200 78.510 5.4 2310100300050 1.240 85.480 5.4 2310100300051 1.280 92.710 5.4 2310100300052 1.320 100.700 5.5 2310100300053 1.360 110.000 5.5 2310100300054 1.400 121.400 6.1 2310100300055 1.440 130.100 6.2 2310100300056 1.480 137.600 5.5 2310100300057 1.520 144.500 5.2 2310100300058 1.560 150.600 5.0 2310100300059 1.600 154.100 5.9 2310100300060 1.640 163.500 6.4 2310100300061 1.680 172.900 6.3 2310100300062 1.720 181.800 5.9 2310100300063 1.760 190.500 5.5 2310100300064 1.800 199.300 5.2 2310100300065 1.840 207.100 5.4 2310100300066 1.880 218.500 5.7 2310100300067 1.920 231.400 6.2 2310100300068 1.960 237.800 5.8 2310100300069 2.000 242.700 5.6 2310100300070 2.040 246.600 5.1 2310100300071 2.080 246.700 5.1 2310100300072 2.120 251.000 5.2 2310100300073 2.160 258.600 4.9 2310100300074 2.200 266.000 4.9 2310100300075 2.240 273.200 5.2 2310100300076 2.280 280.200 5.1 2310100300077 2.320 286.800 5.2 2310100300078 2.360 293.100 5.2 2310100300079 2.400 298.900 5.0 2310100300080 2.440 304.400 5.1 2310100300081 2.480 309.700 5.1 2310100300082 2.520 314.600 5.3 2310100300083 2.560 319.700 5.2 2310100300084 2.600 324.600 5.1 2310100300085 2.640 329.500 5.3 2310100300086 2.680 334.500 5.2 2310100300087 2.720 341.700 5.5 2310100300088 2.760 342.100 5.6 2310100300089 2.800 337.500 5.2 2310100300090 2.840 330.800 5.1 2310100300091 2.880 319.300 5.1 2310100300092 2.920 317.100 5.1 2310100300093 2.960 315.100 5.1 2310100300094 3.000 313.300 5.2 2310100300095 3.040 311.500 5.0 2310100300096 3.080 309.700 5.1 2310100300097 3.120 308.000 5.2 2310100300098 3.160 306.300 5.0 2310100300099 3.200 304.300 5.0 2310100300100 3.240 302.500 5.1 2310100300101 3.280 300.900 5.0 2310100300102 3.320 299.500 5.2 2310100300103 3.360 297.800 5.0 2310100300104 3.400 295.700 5.0 2310100300105 3.440 292.900 5.1 2310100300106 3.480 289.700 5.1 2310100300107 3.520 286.200 5.3 2310100300108 3.560 282.200 5.0 2310100300109 3.600 277.900 5.4 2310100300110 3.640 272.800 5.4 2310100300111 3.680 268.800 5.5 2310100300112 3.720 266.000 5.3 2310100300113 3.760 263.600 5.5 2310100300114 3.800 261.200 5.4 2310100300115 3.840 258.900 5.4 2310100300116 3.880 256.500 5.3 2310100300117 3.920 254.500 5.3 2310100300118 3.960 252.500 5.3 2310100300119 4.000 250.700 5.5 2310100300120 4.040 249.000 5.2 2310100300121 4.080 247.400 5.4 2310100300122 4.120 246.000 5.3 2310100300123 4.160 244.100 5.4 2310100300124 4.200 242.600 5.6 2310100300125 4.240 244.300 5.4 2310100300126 4.280 247.600 5.5 2310100300127 4.320 253.600 5.4 2310100300128 4.360 254.300 5.6 2310100300129 4.400 255.400 5.6 2310100300130 4.440 256.800 5.4 2310100300131 4.480 258.700 5.3 2310100300132 4.520 260.900 5.3 2310100300133 4.560 263.700 5.2 2310100300134 4.600 267.200 5.3 2310100300135 4.640 271.500 5.3 2310100300136 4.680 278.400 5.2 2310100300137 4.720 282.500 5.1 2310100300138 4.760 283.800 5.2 2310100300139 4.800 284.600 5.5 2310100300140 4.840 286.900 5.5 2310100300141 4.880 290.000 5.5 2310100300142 4.920 293.300 5.6 2310100300143 4.960 296.900 5.4 2310100300144 5.000 300.700 5.2 2310100300145 5.040 304.700 5.2 2310100300146 5.080 309.000 5.2 2310100300147 5.120 313.700 5.0 2310100300148 5.160 318.900 5.0 2310100300149 5.200 325.900 5.2 2310100300150 5.240 329.800 5.1 2310100300151 5.280 334.000 5.4 2310100300152 5.320 339.600 5.5 2310100300153 5.360 343.800 5.5 2310100300154 5.400 345.500 5.6 2310100300155 5.440 346.700 5.4 2310100300156 5.480 347.500 5.3 2310100300157 5.520 348.000 5.2 2310100300158 5.560 347.800 5.1 2310100300159 5.600 346.800 5.1 2310100300160 ENDDATA 131 0 2310100300161 ENDSUBENT 160 0 2310100399999 ENDENTRY 3 0 2310199999999