ENTRY 10817 20110727 13741081700000001 SUBENT 10817001 20110727 13741081700100001 BIB 11 25 1081700100002 INSTITUTE (1USAOHO) 1081700100003 REFERENCE (J,NP/A,341,56,198005) 1081700100004 (T,MIRZAA,1978) 1081700100005 AUTHOR (J.Rapaport,M.Mirzaa,H.Hadizadeh,D.E.Bainum, 1081700100006 R.W.Finlay) 1081700100007 TITLE Neutron elastic scattering from Sn-116,118,120,122,124.1081700100008 FACILITY (VDGT,1USAOHO) 11-MeV tandem Van de Graaff 1081700100009 INC-SOURCE (P-T) Protons on tritium for 5-8 MeV neutrons 1081700100010 (D-D) Deuterons on deuterium for 8-12 MeV neutrons 1081700100011 (D-T) Deuterons on tritium for 20-26 MeV neutrons 1081700100012 INC-SPECT Beam pulse duration checked by scattering from gold 1081700100013 foils 1081700100014 METHOD (TOF) Time-of-flight. 1081700100015 ERR-ANALYS Incident neutron energy spread due to- 1081700100016 -energy losses in gas cells 1081700100017 -energy straggling 1081700100018 -angle straggling 1081700100019 STATUS (APRVD) Approved by R.W.Finlay, 1980/6/24. 1081700100020 (TABLE) Data taken from private comm.,Rapaport,1980/6/51081700100021 HISTORY (19800508C) 1081700100022 (19801204A) Reference removed. Subents 11-19 deleted. 1081700100023 (19860319A) BIB correction. 1081700100024 (20110727A) SD:Updated to new date formats,lower case. 1081700100025 corrected according to last EXFOR rules and Dict. 1081700100026 DATA => DATA-CM in Subents 006-010 1081700100027 ENDBIB 25 0 1081700100028 NOCOMMON 0 0 1081700100029 ENDSUBENT 28 0 1081700199999 SUBENT 10817002 20110727 13741081700200001 BIB 7 19 1081700200002 REACTION (50-SN-118(N,TOT),,SIG) 1081700200003 SAMPLE Sample contained in stainless steel holder 1081700200004 DETECTOR (SCIN) Bubble free NE-224 liquid scintillator with 1081700200005 aluminum cell used as main detector. Monitor detector 1081700200006 is 18.4-cm diameter by 5.08-cm thick NE-224 liquid 1081700200007 scintillator with layers of mu-metal to shield 1081700200008 detector from magnetic fields 1081700200009 INC-SPECT Energy and energy spread of incident neutrons 1081700200010 determined from total cross sections of carbon. 1081700200011 METHOD (TRN) Transmission measurement. Detector shadowed 1081700200012 from neutron source by sample. Sample-source distance 1081700200013 is 60-cm. 1081700200014 CORRECTION In-scattering corrections were estimated to be less 1081700200015 than 0.5% and were not included. 1081700200016 ERR-ANALYS (DATA-ERR) Sources of uncertainty include- 1081700200017 -statistics 1081700200018 -in-scattering 1081700200019 -hardening effects 1081700200020 All sources contribute less than 1% each. 1081700200021 ENDBIB 19 0 1081700200022 NOCOMMON 0 0 1081700200023 DATA 3 63 1081700200024 EN DATA DATA-ERR 1081700200025 MEV B PER-CENT 1081700200026 5.049 4.19 1.0 1081700200027 5.252 4.00 1.0 1081700200028 5.457 4.11 1.0 1081700200029 5.864 4.25 1.0 1081700200030 6.068 4.05 1.1 1081700200031 6.170 4.01 1.1 1081700200032 6.474 4.14 1.1 1081700200033 6.775 4.08 1.2 1081700200034 6.878 4.06 1.2 1081700200035 7.080 4.03 1.2 1081700200036 7.285 4.28 1.2 1081700200037 7.488 4.24 1.2 1081700200038 7.680 4.26 1.2 1081700200039 7.917 4.05 1.4 1081700200040 8.130 3.63 1.5 1081700200041 8.290 4.32 1.0 1081700200042 8.340 4.34 1.0 1081700200043 8.390 4.27 1.0 1081700200044 8.440 4.25 1.0 1081700200045 8.490 4.21 1.0 1081700200046 8.510 4.27 1.0 1081700200047 8.530 4.24 1.0 1081700200048 8.550 4.26 1.0 1081700200049 8.570 4.25 1.0 1081700200050 8.590 4.34 1.0 1081700200051 8.610 4.27 1.0 1081700200052 8.630 4.29 1.0 1081700200053 8.650 4.23 1.0 1081700200054 8.670 4.29 1.0 1081700200055 8.690 4.30 1.0 1081700200056 8.750 4.28 1.0 1081700200057 8.790 4.27 1.0 1081700200058 8.810 4.29 1.0 1081700200059 8.830 4.24 1.0 1081700200060 8.850 4.25 1.0 1081700200061 8.870 4.21 1.0 1081700200062 8.890 4.25 1.0 1081700200063 8.910 4.21 1.0 1081700200064 8.930 4.33 1.0 1081700200065 8.950 4.31 1.0 1081700200066 8.970 4.29 1.0 1081700200067 8.990 4.34 1.0 1081700200068 9.040 4.33 1.0 1081700200069 9.090 4.30 1.0 1081700200070 9.110 4.32 1.0 1081700200071 9.130 4.38 1.0 1081700200072 9.150 4.40 1.0 1081700200073 9.170 4.37 1.0 1081700200074 9.190 4.40 1.0 1081700200075 9.210 4.33 1.0 1081700200076 9.230 4.32 1.0 1081700200077 9.250 4.35 1.0 1081700200078 9.270 4.35 1.0 1081700200079 9.290 4.34 1.0 1081700200080 9.340 4.43 1.0 1081700200081 9.390 4.50 1.0 1081700200082 9.490 4.40 1.0 1081700200083 20.005 4.00 2.0 1081700200084 21.024 4.02 2.0 1081700200085 22.000 3.67 2.0 1081700200086 23.000 3.71 2.0 1081700200087 24.000 3.57 2.0 1081700200088 26.000 3.47 3.0 1081700200089 ENDDATA 65 0 1081700200090 ENDSUBENT 89 0 1081700299999 SUBENT 10817003 20110727 13741081700300001 BIB 7 19 1081700300002 REACTION (50-SN-120(N,TOT),,SIG) 1081700300003 SAMPLE Sample contained in stainless steel holder 1081700300004 DETECTOR (SCIN) Bubble free NE-224 liquid scintillator with 1081700300005 aluminum cell used as main detector. Monitor detector 1081700300006 is 18.4-cm diameter by 5.08-cm thick NE-224 liquid 1081700300007 scintillator with layers of mu-metal to shield 1081700300008 detector from magnetic fields 1081700300009 INC-SPECT Energy and energy spread of incident neutrons 1081700300010 determined from total cross sections of carbon. 1081700300011 METHOD (TRN) Transmission measurement. Detector shadowed 1081700300012 from neutron source by sample. Sample-source distance 1081700300013 is 60-cm. 1081700300014 CORRECTION In-scattering corrections were estimated to be less 1081700300015 than 0.5% and were not included. 1081700300016 ERR-ANALYS (DATA-ERR) Sources of uncertainty include- 1081700300017 -statistics 1081700300018 -in-scattering 1081700300019 -hardening effects 1081700300020 All sources contribute less than 1% each. 1081700300021 ENDBIB 19 0 1081700300022 NOCOMMON 0 0 1081700300023 DATA 3 99 1081700300024 EN DATA DATA-ERR 1081700300025 MEV B PER-CENT 1081700300026 5.049 4.15 1.0 1081700300027 5.252 4.05 1.0 1081700300028 5.457 3.97 1.0 1081700300029 5.864 4.22 1.0 1081700300030 6.068 4.09 1.0 1081700300031 6.170 4.00 1.1 1081700300032 6.474 4.19 1.1 1081700300033 6.775 4.21 1.1 1081700300034 6.878 4.09 1.1 1081700300035 7.080 4.13 1.2 1081700300036 7.285 4.18 1.2 1081700300037 7.488 4.22 1.2 1081700300038 7.680 4.12 1.2 1081700300039 7.917 4.28 1.2 1081700300040 8.130 4.06 1.3 1081700300041 8.290 4.29 1.0 1081700300042 8.340 4.26 1.0 1081700300043 8.390 4.28 1.0 1081700300044 8.440 4.32 1.0 1081700300045 8.490 4.38 1.0 1081700300046 8.510 4.31 1.0 1081700300047 8.530 4.28 1.0 1081700300048 8.550 4.34 1.0 1081700300049 8.570 4.24 1.0 1081700300050 8.590 4.32 1.0 1081700300051 8.610 4.34 1.0 1081700300052 8.630 4.31 1.0 1081700300053 8.650 4.29 1.0 1081700300054 8.670 4.32 1.0 1081700300055 8.690 4.32 1.0 1081700300056 8.750 4.23 1.0 1081700300057 8.790 4.32 1.0 1081700300058 8.810 4.34 1.0 1081700300059 8.830 4.34 1.0 1081700300060 8.850 4.27 1.0 1081700300061 8.870 4.22 1.0 1081700300062 8.890 4.29 1.0 1081700300063 8.910 4.45 1.0 1081700300064 8.930 4.27 1.0 1081700300065 8.950 4.28 1.0 1081700300066 8.970 4.37 1.0 1081700300067 8.990 4.42 1.0 1081700300068 9.040 4.23 1.0 1081700300069 9.090 4.37 1.0 1081700300070 9.110 4.29 1.0 1081700300071 9.130 4.53 1.0 1081700300072 9.150 4.39 1.0 1081700300073 9.170 4.40 1.0 1081700300074 9.190 4.37 1.0 1081700300075 9.210 4.42 1.0 1081700300076 9.230 4.44 1.0 1081700300077 9.250 4.51 1.0 1081700300078 9.270 4.30 1.0 1081700300079 9.290 4.47 1.0 1081700300080 9.390 4.47 1.0 1081700300081 9.490 4.51 1.0 1081700300082 9.590 4.46 1.0 1081700300083 9.690 4.48 1.0 1081700300084 9.740 4.46 1.0 1081700300085 9.760 4.48 1.0 1081700300086 9.780 4.41 1.0 1081700300087 9.800 4.56 1.0 1081700300088 9.820 4.47 1.0 1081700300089 9.840 4.46 1.0 1081700300090 9.860 4.43 1.0 1081700300091 9.880 4.47 1.0 1081700300092 9.900 4.44 1.0 1081700300093 9.920 4.41 1.0 1081700300094 9.940 4.48 1.0 1081700300095 9.990 4.61 1.0 1081700300096 10.04 4.50 1.0 1081700300097 10.09 4.47 1.0 1081700300098 10.11 4.45 1.0 1081700300099 10.13 4.44 1.0 1081700300100 10.15 4.49 1.0 1081700300101 10.17 4.51 1.0 1081700300102 10.19 4.47 1.0 1081700300103 10.21 4.42 1.0 1081700300104 10.23 4.40 1.0 1081700300105 10.25 4.45 1.0 1081700300106 10.29 4.47 1.0 1081700300107 10.34 4.44 1.0 1081700300108 10.36 4.47 1.0 1081700300109 10.38 4.46 1.0 1081700300110 10.41 4.53 1.0 1081700300111 10.42 4.57 1.0 1081700300112 10.44 4.51 1.0 1081700300113 10.46 4.50 1.0 1081700300114 10.48 4.47 1.0 1081700300115 10.50 4.40 1.0 1081700300116 10.52 4.43 1.0 1081700300117 10.54 4.46 1.0 1081700300118 10.59 4.48 1.0 1081700300119 20.00 4.12 2.0 1081700300120 21.00 3.91 2.0 1081700300121 22.00 3.75 2.0 1081700300122 23.00 3.91 2.0 1081700300123 24.00 3.72 2.0 1081700300124 26.00 3.50 2.0 1081700300125 ENDDATA 101 0 1081700300126 ENDSUBENT 125 0 1081700399999 SUBENT 10817004 20110727 13741081700400001 BIB 7 19 1081700400002 REACTION (50-SN-122(N,TOT),,SIG) 1081700400003 SAMPLE Sample contained in stainless steel holder 1081700400004 DETECTOR (SCIN) Bubble free NE-224 liquid scintillator with 1081700400005 aluminum cell used as main detector. Monitor detector 1081700400006 is 18.4-cm diameter by 5.08-cm thick NE-224 liquid 1081700400007 scintillator with layers of mu-metal to shield 1081700400008 detector from magnetic fields 1081700400009 MONITOR Energy and energy spread of incident neutrons 1081700400010 determined from total cross sections of carbon. 1081700400011 METHOD (TRN) Transmission measurement. Detector shadowed 1081700400012 from neutron source by sample. Sample-source distance 1081700400013 is 60-cm. 1081700400014 CORRECTION In-scattering corrections were estimated to be less 1081700400015 than 0.5% and were not included. 1081700400016 ERR-ANALYS (DATA-ERR) Sources of uncertainty include- 1081700400017 -statistics 1081700400018 -in-scattering 1081700400019 -hardening effects 1081700400020 All sources contribute less than 1% each. 1081700400021 ENDBIB 19 0 1081700400022 NOCOMMON 0 0 1081700400023 DATA 3 21 1081700400024 EN DATA DATA-ERR 1081700400025 MEV B PER-CENT 1081700400026 5.049 4.29 1.3 1081700400027 5.252 3.95 2.0 1081700400028 5.457 3.92 2.0 1081700400029 5.864 4.26 1.0 1081700400030 6.068 4.14 2.0 1081700400031 6.170 4.00 2.0 1081700400032 6.474 4.49 2.0 1081700400033 6.775 4.18 2.0 1081700400034 6.878 4.17 2.0 1081700400035 7.080 3.88 2.0 1081700400036 7.285 4.43 2.0 1081700400037 7.488 4.29 2.0 1081700400038 7.680 4.28 1.0 1081700400039 7.917 4.59 2.0 1081700400040 8.130 4.49 2.0 1081700400041 20.00 4.37 3.0 1081700400042 21.00 4.22 3.0 1081700400043 22.00 4.07 3.0 1081700400044 23.00 4.07 3.0 1081700400045 24.00 3.88 3.0 1081700400046 26.00 3.55 4.0 1081700400047 ENDDATA 23 0 1081700400048 ENDSUBENT 47 0 1081700499999 SUBENT 10817005 20110727 13741081700500001 BIB 7 19 1081700500002 REACTION (50-SN-124(N,TOT),,SIG) 1081700500003 SAMPLE Sample contained in stainless steel holder 1081700500004 DETECTOR (SCIN) Bubble free NE-224 liquid scintillator with 1081700500005 aluminum cell used as main detector. Monitor detector 1081700500006 is 18.4-cm diameter by 5.08-cm thick NE-224 liquid 1081700500007 scintillator with layers of mu-metal to shield 1081700500008 detector from magnetic fields 1081700500009 INC-SPECT Energy and energy spread of incident neutrons 1081700500010 determined from total cross sections of carbon. 1081700500011 METHOD (TRN) Transmission measurement. Detector shadowed 1081700500012 from neutron source by sample. Sample-source distance 1081700500013 is 60-cm. 1081700500014 CORRECTION In-scattering corrections were estimated to be less 1081700500015 than 0.5% and were not included. 1081700500016 ERR-ANALYS (DATA-ERR) Sources of uncertainty include- 1081700500017 -statistics 1081700500018 -in-scattering 1081700500019 -hardening effects 1081700500020 All sources contribute less than 1% each. 1081700500021 ENDBIB 19 0 1081700500022 NOCOMMON 0 0 1081700500023 DATA 3 59 1081700500024 EN DATA DATA-ERR 1081700500025 MEV B PER-CENT 1081700500026 5.049 4.29 1.0 1081700500027 5.252 4.06 1.0 1081700500028 5.457 3.97 1.0 1081700500029 5.864 4.29 1.0 1081700500030 6.068 4.18 1.0 1081700500031 6.170 4.21 1.0 1081700500032 6.474 4.21 1.0 1081700500033 6.775 4.06 1.2 1081700500034 6.878 4.19 1.1 1081700500035 7.080 4.14 1.1 1081700500036 7.285 4.31 1.2 1081700500037 7.488 4.10 1.2 1081700500038 7.680 4.51 1.2 1081700500039 7.917 4.60 1.2 1081700500040 8.130 4.36 1.2 1081700500041 9.490 4.59 1.0 1081700500042 9.590 4.51 1.0 1081700500043 9.690 4.51 1.0 1081700500044 9.740 4.44 1.0 1081700500045 9.760 4.59 1.0 1081700500046 9.780 4.41 1.0 1081700500047 9.800 4.76 1.0 1081700500048 9.820 4.57 1.0 1081700500049 9.840 4.56 1.0 1081700500050 9.860 4.53 1.0 1081700500051 9.880 4.72 1.0 1081700500052 9.900 4.53 1.0 1081700500053 9.920 4.56 1.0 1081700500054 9.940 4.65 1.0 1081700500055 9.990 4.57 1.0 1081700500056 10.04 4.51 1.0 1081700500057 10.09 4.46 1.0 1081700500058 10.11 4.64 1.0 1081700500059 10.13 4.49 1.0 1081700500060 10.15 4.54 1.0 1081700500061 10.17 4.66 1.0 1081700500062 10.19 4.63 1.0 1081700500063 10.21 4.53 1.0 1081700500064 10.23 4.52 1.0 1081700500065 10.25 4.59 1.0 1081700500066 10.29 4.43 1.0 1081700500067 10.34 4.53 1.0 1081700500068 10.36 4.62 1.0 1081700500069 10.38 4.51 1.0 1081700500070 10.41 4.62 1.0 1081700500071 10.42 4.78 1.0 1081700500072 10.44 4.57 1.0 1081700500073 10.46 4.60 1.0 1081700500074 10.48 4.48 1.0 1081700500075 10.50 4.41 1.0 1081700500076 10.52 4.48 1.0 1081700500077 10.54 4.46 1.0 1081700500078 10.59 4.61 1.0 1081700500079 20.00 4.13 2.0 1081700500080 21.00 4.18 2.0 1081700500081 22.00 3.95 2.0 1081700500082 23.00 3.86 2.0 1081700500083 24.00 3.48 2.0 1081700500084 26.00 3.66 2.0 1081700500085 ENDDATA 61 0 1081700500086 ENDSUBENT 85 0 1081700599999 SUBENT 10817006 20110727 13741081700600001 BIB 7 33 1081700600002 REACTION (50-SN-116(N,EL)50-SN-116,,DA) 1081700600003 SAMPLE Sample enclosed in aluminum holder hung vertically in 1081700600004 beam by a thin wire. 1081700600005 DETECTOR (SCIN) NE-224 liquid scintillator, 18.4-cm diameter, 1081700600006 5.08-cm thick, for runs with 11-MeV incident neutrons.1081700600007 24-MeV incident neutron runs used a 29.2-cm thick, 1081700600008 18.4-cm diameter NE-224 liquid scintillator. Both are 1081700600009 shielded from magnetic fields with layers of mu-metal.1081700600010 Flux monitor is a bubble free NE-224 liquid 1081700600011 scintillator in an aluminum cell. 1081700600012 METHOD (TOF) 6.6-meter flight path used. Main detectors placed1081700600013 inside water tank to insure radiation shielding. Front1081700600014 of water tank shielded by iron and paraffin and used 1081700600015 a copper shadow bar. Computer code PKFIT used to 1081700600016 extract peak areas from time of flight spectra. 1081700600017 Dead time, source anisotropy, and detector efficiency.1081700600018 CORRECTION Data corrected for background, finite sample size, 1081700600019 dead time, source anisotropy, and detector efficiency.1081700600020 ERR-ANALYS (ERR-T,5.,15.) Total uncertainty includes: 1081700600021 -statistics in yields 1081700600022 -monitor statistics 1081700600023 -multiple scattering statistics 1081700600024 -Monte Carlo statistics 1081700600025 -inelastic scattering contributions 1081700600026 -compound nucleus contribution 1081700600027 -scattering angle 1081700600028 -detector efficiency 1081700600029 (DATA-ERR) Absolute uncertainties include- 1081700600030 -geometrical factors 1081700600031 -statistics in yields 1081700600032 -monitor statistics 1081700600033 -monitor residual background 1081700600034 HISTORY (20110727A) SD: DATA => DATA-CM 1081700600035 ENDBIB 33 0 1081700600036 NOCOMMON 0 0 1081700600037 DATA 4 61 1081700600038 EN ANG-CM DATA-CM DATA-ERR 1081700600039 MEV ADEG MB/SR MB/SR 1081700600040 11. 15.1 3617. 109. 1081700600041 11. 20.2 2046. 61.0 1081700600042 11. 25.2 919.6 28.0 1081700600043 11. 30.3 299.3 9.00 1081700600044 11. 35.3 60.84 1.80 1081700600045 11. 40.4 58.10 1.74 1081700600046 11. 45.4 122.0 3.70 1081700600047 11. 50.4 160.6 4.80 1081700600048 11. 55.4 148.7 4.50 1081700600049 11. 60.5 112.4 3.40 1081700600050 11. 65.5 65.38 2.30 1081700600051 11. 70.5 29.95 1.05 1081700600052 11. 75.5 11.51 0.400 1081700600053 11. 80.5 5.780 0.230 1081700600054 11. 85.5 8.440 0.250 1081700600055 11. 90.6 14.13 0.570 1081700600056 11. 95.5 20.19 0.850 1081700600057 11. 100.5 24.00 0.840 1081700600058 11. 105.5 22.99 0.800 1081700600059 11. 110.5 17.35 0.610 1081700600060 11. 115.5 10.78 0.430 1081700600061 11. 120.5 6.520 0.290 1081700600062 11. 125.4 4.860 0.270 1081700600063 11. 130.4 7.300 0.290 1081700600064 11. 135.4 9.700 0.390 1081700600065 11. 140.4 10.95 0.440 1081700600066 11. 145.3 10.52 0.740 1081700600067 11. 150.3 8.310 0.660 1081700600068 24. 15.1 2592. 130. 1081700600069 24. 20.2 685.3 34.3 1081700600070 24. 25.2 98.56 4.97 1081700600071 24. 30.2 51.38 3.63 1081700600072 24. 32.8 62.31 3.12 1081700600073 24. 35.3 61.19 3.06 1081700600074 24. 37.8 45.41 2.27 1081700600075 24. 40.3 28.67 1.43 1081700600076 24. 42.8 19.92 1.20 1081700600077 24. 45.3 13.81 0.990 1081700600078 24. 47.9 27.97 1.40 1081700600079 24. 50.4 38.94 1.94 1081700600080 24. 55.4 67.97 3.40 1081700600081 24. 60.4 60.58 3.03 1081700600082 24. 65.4 38.40 1.92 1081700600083 24. 70.5 24.99 1.25 1081700600084 24. 75.5 23.36 1.17 1081700600085 24. 80.5 27.39 1.37 1081700600086 24. 85.5 25.51 1.28 1081700600087 24. 90.5 20.30 1.02 1081700600088 24. 95.5 12.10 0.650 1081700600089 24. 100.5 8.150 0.510 1081700600090 24. 105.5 8.820 0.500 1081700600091 24. 110.5 11.28 0.570 1081700600092 24. 115.4 9.650 0.530 1081700600093 24. 120.4 6.650 0.420 1081700600094 24. 125.4 3.850 0.380 1081700600095 24. 130.4 2.700 0.290 1081700600096 24. 135.3 4.080 0.440 1081700600097 24. 140.3 4.980 0.400 1081700600098 24. 145.3 3.260 0.320 1081700600099 24. 150.2 1.680 0.250 1081700600100 24. 155.2 3.800 0.490 1081700600101 ENDDATA 63 0 1081700600102 ENDSUBENT 101 0 1081700699999 SUBENT 10817007 20110727 13741081700700001 BIB 7 32 1081700700002 REACTION (50-SN-118(N,EL)50-SN-118,,DA) 1081700700003 SAMPLE Sample enclosed in aluminum holder hung vertically in 1081700700004 beam by a thin wire. 1081700700005 DETECTOR (SCIN) NE-224 liquid scintillator, 18.4-cm diameter, 1081700700006 5.08-cm thick, for runs with 11-MeV incident neutrons.1081700700007 24-MeV incident neutron runs used a 29.2-cm thick, 1081700700008 18.4-cm diameter NE-224 liquid scintillator. Both are 1081700700009 shielded from magnetic fields with layers of mu-metal.1081700700010 Flux monitor is a bubble free NE-224 liquid 1081700700011 scintillator in an aluminum cell. 1081700700012 METHOD (TOF) 6.6-Meter flight path used. Main detectors placed1081700700013 inside water tank to insure radiation shielding. Front1081700700014 of water tank shielded by iron and paraffin and used 1081700700015 a copper shadow bar. Computer code PKFIT used to 1081700700016 extract peak areas from time of flight spectra. 1081700700017 CORRECTION Data corrected for background, finite sample size, 1081700700018 dead time, source anisotropy, and detector efficiency.1081700700019 ERR-ANALYS (ERR-T,5.,15.) Total uncertainty includes: 1081700700020 -statistics in yields 1081700700021 -monitor statistics 1081700700022 -multiple scattering statistics 1081700700023 -Monte Carlo statistics 1081700700024 -inelastic scattering contributions 1081700700025 -compound nucleus contribution 1081700700026 -scattering angle 1081700700027 -detector efficiency 1081700700028 (DATA-ERR) Absolute uncertainties include- 1081700700029 -geometrical factors 1081700700030 -statistics in yields 1081700700031 -monitor statistics 1081700700032 -monitor residual background 1081700700033 HISTORY (20110727A) SD: DATA => DATA-CM 1081700700034 ENDBIB 32 0 1081700700035 NOCOMMON 0 0 1081700700036 DATA 4 53 1081700700037 EN ANG-CM DATA-CM DATA-ERR 1081700700038 MEV ADEG MB/SR MB/SR 1081700700039 11. 15.1 3676. 110. 1081700700040 11. 20.2 2152. 64.6 1081700700041 11. 25.2 936.0 28.1 1081700700042 11. 30.2 346.9 10.4 1081700700043 11. 35.3 69.59 2.09 1081700700044 11. 40.3 59.42 1.78 1081700700045 11. 45.3 129.7 3.89 1081700700046 11. 50.4 165.7 4.97 1081700700047 11. 55.4 158.8 4.76 1081700700048 11. 60.4 117.6 3.53 1081700700049 11. 65.4 67.06 2.01 1081700700050 11. 70.5 31.77 0.950 1081700700051 11. 75.5 12.92 0.390 1081700700052 11. 80.5 6.590 0.240 1081700700053 11. 85.5 7.530 0.340 1081700700054 11. 90.5 16.57 0.500 1081700700055 11. 95.5 21.31 0.640 1081700700056 11. 100.5 24.08 0.720 1081700700057 11. 105.5 23.27 0.700 1081700700058 11. 110.5 17.42 0.520 1081700700059 11. 115.4 10.88 0.330 1081700700060 11. 120.4 5.680 0.170 1081700700061 11. 125.4 6.190 0.280 1081700700062 11. 130.4 8.070 0.320 1081700700063 11. 135.3 10.22 0.370 1081700700064 11. 140.3 11.19 0.380 1081700700065 11. 145.3 10.95 0.380 1081700700066 11. 150.2 11.65 0.370 1081700700067 24. 15.1 2592. 5.80 1081700700068 24. 20.2 788.7 7.60 1081700700069 24. 25.2 106.1 5.00 1081700700070 24. 30.2 48.00 0.700 1081700700071 24. 35.3 59.80 0.700 1081700700072 24. 40.3 26.60 0.600 1081700700073 24. 45.3 21.00 0.300 1081700700074 24. 50.4 52.80 1081700700075 24. 55.4 70.40 0.100 1081700700076 24. 60.4 57.90 0.600 1081700700077 24. 65.4 36.30 0.200 1081700700078 24. 70.5 17.50 0.100 1081700700079 24. 75.5 22.60 0.500 1081700700080 24. 80.5 27.10 0.600 1081700700081 24. 85.5 25.90 0.600 1081700700082 24. 90.5 16.80 0.200 1081700700083 24. 95.5 11.50 0.760 1081700700084 24. 100.5 7.570 0.550 1081700700085 24. 105.5 6.330 0.850 1081700700086 24. 110.5 9.730 0.720 1081700700087 24. 115.4 12.00 0.300 1081700700088 24. 120.4 6.710 0.800 1081700700089 24. 125.4 4.600 0.760 1081700700090 24. 130.4 3.810 0.490 1081700700091 24. 140.3 5.450 0.530 1081700700092 ENDDATA 55 0 1081700700093 ENDSUBENT 92 0 1081700799999 SUBENT 10817008 20110727 13741081700800001 BIB 7 32 1081700800002 REACTION (50-SN-120(N,EL)50-SN-120,,DA) 1081700800003 SAMPLE Sample enclosed in aluminum holder hung vertically in 1081700800004 beam by a thin wire. 1081700800005 DETECTOR (SCIN) NE-224 liquid scintillator, 18.4-cm diameter, 1081700800006 5.08-cm thick, for runs with 11-MeV incident neutrons.1081700800007 24-MeV incident neutron runs used a 29.2-cm thick, 1081700800008 18.4-cm diameter NE-224 liquid scintillator. Both are 1081700800009 shielded from magnetic fields with layers of mu-metal.1081700800010 Flux monitor is a bubble free NE-224 liquid 1081700800011 scintillator in an aluminum cell. 1081700800012 METHOD (TOF) 6.6-Meter flight path used. Main detectors placed1081700800013 inside water tank to insure radiation shielding. Front1081700800014 of water tank shielded by iron and paraffin and used 1081700800015 a copper shadow bar. Computer code PKFIT used to 1081700800016 extract peak areas from time of flight spectra. 1081700800017 CORRECTION Data corrected for background, finite sample size, 1081700800018 dead time, source anisotropy, and detector efficiency.1081700800019 ERR-ANALYS (ERR-T,5.,15.) Total uncertainty includes: 1081700800020 -statistics in yields 1081700800021 -monitor statistics 1081700800022 -multiple scattering statistics 1081700800023 -Monte Carlo statistics 1081700800024 -inelastic scattering contributions 1081700800025 -compound nucleus contribution 1081700800026 -scattering angle 1081700800027 -detector efficiency 1081700800028 (DATA-ERR) Absolute uncertainties include- 1081700800029 -geometrical factors 1081700800030 -statistics in yields 1081700800031 -monitor statistics 1081700800032 -monitor residual background 1081700800033 HISTORY (20110727A) SD: DATA => DATA-CM 1081700800034 ENDBIB 32 0 1081700800035 COMMON 1 3 1081700800036 EN 1081700800037 MEV 1081700800038 11.0 1081700800039 ENDCOMMON 3 0 1081700800040 DATA 3 28 1081700800041 ANG-CM DATA-CM DATA-ERR 1081700800042 ADEG MB/SR MB/SR 1081700800043 15.1 3745. 112. 1081700800044 20.2 2103. 63.1 1081700800045 25.2 883.9 2.83 1081700800046 30.2 303.5 9.11 1081700800047 35.3 71.28 2.14 1081700800048 40.3 70.02 2.10 1081700800049 45.3 135.7 4.07 1081700800050 50.4 172.1 5.16 1081700800051 55.4 156.2 4.69 1081700800052 60.4 118.1 3.54 1081700800053 65.4 67.77 2.03 1081700800054 70.4 30.94 0.930 1081700800055 75.5 14.03 0.420 1081700800056 80.5 7.040 0.210 1081700800057 85.5 9.160 0.270 1081700800058 90.5 16.69 0.500 1081700800059 95.5 22.30 0.670 1081700800060 100.5 25.24 0.760 1081700800061 105.5 23.78 0.710 1081700800062 110.4 17.17 0.520 1081700800063 115.4 10.61 0.320 1081700800064 120.4 4.830 0.160 1081700800065 125.4 5.940 0.280 1081700800066 130.4 9.160 0.360 1081700800067 135.3 13.33 0.430 1081700800068 140.3 13.83 0.420 1081700800069 145.3 11.34 0.380 1081700800070 150.2 11.13 0.370 1081700800071 ENDDATA 30 0 1081700800072 ENDSUBENT 71 0 1081700899999 SUBENT 10817009 20110727 13741081700900001 BIB 7 32 1081700900002 REACTION (50-SN-122(N,EL)50-SN-122,,DA) 1081700900003 SAMPLE Sample enclosed in aluminum holder hung vertically in 1081700900004 beam by a thin wire. 1081700900005 DETECTOR (SCIN) NE-224 liquid scintillator, 18.4-cm diameter, 1081700900006 5.08-cm thick, for runs with 11-MeV incident neutrons.1081700900007 24-MeV incident neutron runs used a 29.2-cm thick, 1081700900008 18.4-cm diameter NE-224 liquid scintillator. Both are 1081700900009 shielded from magnetic fields with layers of mu-metal.1081700900010 Flux monitor is a bubble free NE-224 liquid 1081700900011 scintillator in an aluminum cell. 1081700900012 METHOD (TOF) 6.6-Meter flight path used. Main detectors placed1081700900013 inside water tank to insure radiation shielding. Front1081700900014 of water tank shielded by iron and paraffin and used 1081700900015 a copper shadow bar. Computer code PKFIT used to 1081700900016 extract peak areas from time of flight spectra. 1081700900017 CORRECTION Data corrected for background, finite sample size, 1081700900018 dead time, source anisotropy, and detector efficiency.1081700900019 ERR-ANALYS (ERR-T,5.,15.) Total uncertainty includes: 1081700900020 -statistics in yields 1081700900021 -monitor statistics 1081700900022 -multiple scattering statistics 1081700900023 -Monte Carlo statistics 1081700900024 -inelastic scattering contributions 1081700900025 -compound nucleus contribution 1081700900026 -scattering angle 1081700900027 -detector efficiency 1081700900028 (DATA-ERR) Absolute uncertainties include- 1081700900029 -geometrical factors 1081700900030 -statistics in yields 1081700900031 -monitor statistics 1081700900032 -monitor residual background 1081700900033 HISTORY (20110727A) SD: DATA => DATA-CM 1081700900034 ENDBIB 32 0 1081700900035 COMMON 1 3 1081700900036 EN 1081700900037 MEV 1081700900038 11.0 1081700900039 ENDCOMMON 3 0 1081700900040 DATA 3 28 1081700900041 ANG-CM DATA-CM DATA-ERR 1081700900042 ADEG MB/SR MB/SR 1081700900043 15.1 3914. 117. 1081700900044 20.2 2168. 65.0 1081700900045 25.2 920.0 27.6 1081700900046 30.2 322.4 9.67 1081700900047 35.3 76.17 2.29 1081700900048 40.3 77.75 2.33 1081700900049 45.3 150.6 4.52 1081700900050 50.4 180.6 5.42 1081700900051 55.4 206.8 6.20 1081700900052 60.4 117.5 3.52 1081700900053 65.4 64.54 1.94 1081700900054 70.4 30.98 0.930 1081700900055 75.4 13.36 0.400 1081700900056 80.5 7.760 0.230 1081700900057 85.5 12.10 0.360 1081700900058 90.5 19.86 0.600 1081700900059 95.5 24.44 0.730 1081700900060 100.5 27.21 0.820 1081700900061 105.4 26.30 0.790 1081700900062 110.4 19.40 0.580 1081700900063 115.4 12.61 0.380 1081700900064 120.4 5.890 0.360 1081700900065 125.4 8.280 0.470 1081700900066 130.4 11.70 0.460 1081700900067 135.3 15.14 0.610 1081700900068 140.3 16.08 0.640 1081700900069 145.3 13.59 0.590 1081700900070 150.2 18.67 0.740 1081700900071 ENDDATA 30 0 1081700900072 ENDSUBENT 71 0 1081700999999 SUBENT 10817010 20110727 13741081701000001 BIB 7 32 1081701000002 REACTION (50-SN-124(N,EL)50-SN-124,,DA) 1081701000003 SAMPLE Sample enclosed in aluminum holder hung vertically in 1081701000004 beam by a thin wire. 1081701000005 DETECTOR (SCIN) NE-224 liquid scintillator, 18.4-cm diameter, 1081701000006 5.08-cm thick, for runs with 11-MeV incident neutrons.1081701000007 24-MeV incident neutron runs used a 29.2-cm thick, 1081701000008 18.4-cm diameter NE-224 liquid scintillator. Both are 1081701000009 shielded from magnetic fields with layers of mu-metal.1081701000010 Flux monitor is a bubble free NE-224 liquid 1081701000011 scintillator in an aluminum cell. 1081701000012 METHOD (TOF) 6.6-Meter flight path used. Main detectors placed1081701000013 inside water tank to insure radiation shielding. Front1081701000014 of water tank shielded by iron and paraffin and used 1081701000015 a copper shadow bar. Computer code PKFIT used to 1081701000016 extract peak areas from time of flight spectra. 1081701000017 CORRECTION Data corrected for background, finite sample size, 1081701000018 dead time, source anisotropy, and detector efficiency.1081701000019 ERR-ANALYS (ERR-T,5.,15.) Total uncertainty includes: 1081701000020 -statistics in yields 1081701000021 -monitor statistics 1081701000022 -multiple scattering statistics 1081701000023 -Monte Carlo statistics 1081701000024 -inelastic scattering contributions 1081701000025 -compound nucleus contribution 1081701000026 -scattering angle 1081701000027 -detector efficiency 1081701000028 (DATA-ERR) Absolute uncertainties include- 1081701000029 -geometrical factors 1081701000030 -statistics in yields 1081701000031 -monitor statistics 1081701000032 -monitor residual background 1081701000033 HISTORY (20110727A) SD: DATA => DATA-CM 1081701000034 ENDBIB 32 0 1081701000035 NOCOMMON 0 0 1081701000036 DATA 4 53 1081701000037 EN ANG-CM DATA-CM DATA-ERR 1081701000038 MEV ADEG MB/SR MB/SR 1081701000039 11. 15.1 3777. 113. 1081701000040 11. 20.2 2150. 64.5 1081701000041 11. 25.2 902.4 30.7 1081701000042 11. 30.2 294.3 8.83 1081701000043 11. 35.3 73.97 2.22 1081701000044 11. 40.3 86.31 2.59 1081701000045 11. 45.3 162.6 4.88 1081701000046 11. 50.3 190.1 5.70 1081701000047 11. 55.4 173.0 5.19 1081701000048 11. 60.4 123.0 3.69 1081701000049 11. 65.4 70.57 2.12 1081701000050 11. 70.4 31.02 0.930 1081701000051 11. 75.4 12.79 0.790 1081701000052 11. 80.5 9.160 0.390 1081701000053 11. 85.5 12.79 0.540 1081701000054 11. 90.5 18.88 0.750 1081701000055 11. 95.5 24.17 0.770 1081701000056 11. 100.5 27.16 0.830 1081701000057 11. 105.4 25.68 0.930 1081701000058 11. 110.4 18.71 0.790 1081701000059 11. 115.4 11.12 0.590 1081701000060 11. 120.4 6.150 0.290 1081701000061 11. 125.4 6.760 0.340 1081701000062 11. 130.3 11.51 0.540 1081701000063 11. 135.3 15.59 0.640 1081701000064 11. 140.3 16.05 0.650 1081701000065 11. 145.3 12.33 0.510 1081701000066 11. 150.2 11.52 0.470 1081701000067 24. 15.1 2800. 168. 1081701000068 24. 20.2 729.4 43.8 1081701000069 24. 25.2 92.01 5.54 1081701000070 24. 30.2 44.20 3.86 1081701000071 24. 35.3 47.02 4.55 1081701000072 24. 40.3 22.16 1.57 1081701000073 24. 45.3 17.80 2.23 1081701000074 24. 50.3 55.01 3.20 1081701000075 24. 55.4 79.05 4.72 1081701000076 24. 60.4 53.67 6.10 1081701000077 24. 65.4 36.22 2.19 1081701000078 24. 70.4 21.39 2.10 1081701000079 24. 75.4 26.68 1.63 1081701000080 24. 80.5 32.21 1.93 1081701000081 24. 85.5 23.83 1.45 1081701000082 24. 90.5 19.85 1.44 1081701000083 24. 95.5 13.24 1.19 1081701000084 24. 100.5 11.37 0.980 1081701000085 24. 105.4 9.850 1.62 1081701000086 24. 110.4 11.86 1.22 1081701000087 24. 115.4 10.13 1.20 1081701000088 24. 120.4 6.540 0.720 1081701000089 24. 125.4 4.380 0.580 1081701000090 24. 130.3 5.170 0.860 1081701000091 24. 140.3 5.490 0.990 1081701000092 ENDDATA 55 0 1081701000093 ENDSUBENT 92 0 1081701099999 SUBENT 10817011 20110727 13741081701100001 BIB 2 2 1081701100002 REACTION (50-SN-116(N,INL)50-SN-116,PAR,DA) 1081701100003 HISTORY (19801204A) Deleted.See SANs 10931004,10932002 for data1081701100004 ENDBIB 2 0 1081701100005 COMMON 1 3 1081701100006 Q-VAL 1081701100007 MEV 1081701100008 -2.27 1081701100009 ENDCOMMON 3 0 1081701100010 NODATA 0 0 1081701100011 ENDSUBENT 10 0 1081701199999 SUBENT 10817012 20110727 13741081701200001 BIB 2 2 1081701200002 REACTION (50-SN-116(N,INL)50-SN-116,PAR,DA) 1081701200003 HISTORY (19801204A) Deleted. See SAN 10932003 for data. 1081701200004 ENDBIB 2 0 1081701200005 COMMON 1 3 1081701200006 Q-VAL 1081701200007 MEV 1081701200008 -1.29 1081701200009 ENDCOMMON 3 0 1081701200010 NODATA 0 0 1081701200011 ENDSUBENT 10 0 1081701299999 SUBENT 10817013 20110727 13741081701300001 BIB 2 2 1081701300002 REACTION (50-SN-118(N,INL)50-SN-118,PAR,DA) 1081701300003 HISTORY (19801204A) Deleted. See SAN 10931005 for data. 1081701300004 ENDBIB 2 0 1081701300005 COMMON 2 3 1081701300006 EN Q-VAL 1081701300007 MEV MEV 1081701300008 11. -2.33 1081701300009 ENDCOMMON 3 0 1081701300010 NODATA 0 0 1081701300011 ENDSUBENT 10 0 1081701399999 SUBENT 10817014 20110727 13741081701400001 BIB 2 2 1081701400002 REACTION (50-SN-118(N,INL)50-SN-118,PAR,DA) 1081701400003 HISTORY (19801204A) Deleted. See SAN 10932004 for data. 1081701400004 ENDBIB 2 0 1081701400005 COMMON 2 3 1081701400006 EN Q-VAL 1081701400007 MEV MEV 1081701400008 11. -1.23 1081701400009 ENDCOMMON 3 0 1081701400010 NODATA 0 0 1081701400011 ENDSUBENT 10 0 1081701499999 SUBENT 10817015 20110727 13741081701500001 BIB 2 2 1081701500002 REACTION (50-SN-120(N,INL)50-SN-120,PAR,DA) 1081701500003 HISTORY (19801204A) Deleted. See SAN 10932005 for data. 1081701500004 ENDBIB 2 0 1081701500005 COMMON 2 3 1081701500006 EN Q-VAL 1081701500007 MEV MEV 1081701500008 11. -1.17 1081701500009 ENDCOMMON 3 0 1081701500010 NODATA 0 0 1081701500011 ENDSUBENT 10 0 1081701599999 SUBENT 10817016 20110727 13741081701600001 BIB 2 2 1081701600002 REACTION (50-SN-120(N,INL)50-SN-120,PAR,DA) 1081701600003 HISTORY (19801204A) Deleted. See SAN 10931006 for data. 1081701600004 ENDBIB 2 0 1081701600005 COMMON 2 3 1081701600006 EN Q-VAL 1081701600007 MEV MEV 1081701600008 11. -2.41 1081701600009 ENDCOMMON 3 0 1081701600010 NODATA 0 0 1081701600011 ENDSUBENT 10 0 1081701699999 SUBENT 10817017 20110727 13741081701700001 BIB 2 2 1081701700002 REACTION (50-SN-122(N,INL)50-SN-122,PAR,DA) 1081701700003 HISTORY (19801204A) Deleted. See SAN 10932006 for data. 1081701700004 ENDBIB 2 0 1081701700005 COMMON 2 3 1081701700006 EN Q-VAL 1081701700007 MEV MEV 1081701700008 11. -1.14 1081701700009 ENDCOMMON 3 0 1081701700010 NODATA 0 0 1081701700011 ENDSUBENT 10 0 1081701799999 SUBENT 10817018 20110727 13741081701800001 BIB 2 2 1081701800002 REACTION (50-SN-124(N,INL)50-SN-124,PAR,DA) 1081701800003 HISTORY (19801204A) Deleted. See SAN 10932007 for data. 1081701800004 ENDBIB 2 0 1081701800005 COMMON 2 3 1081701800006 EN Q-VAL 1081701800007 MEV MEV 1081701800008 11. -1.14 1081701800009 ENDCOMMON 3 0 1081701800010 NODATA 0 0 1081701800011 ENDSUBENT 10 0 1081701899999 SUBENT 10817019 20110727 13741081701900001 BIB 2 2 1081701900002 REACTION (50-SN-124(N,INL)50-SN-124,PAR,DA) 1081701900003 HISTORY (19801204A) Deleted. See SAN 10931007 for data. 1081701900004 ENDBIB 2 0 1081701900005 COMMON 2 3 1081701900006 EN Q-VAL 1081701900007 MEV MEV 1081701900008 11. -2.613 1081701900009 ENDCOMMON 3 0 1081701900010 NODATA 0 0 1081701900011 ENDSUBENT 10 0 1081701999999 SUBENT 10817020 20110727 13741081702000001 BIB 8 20 1081702000002 REACTION (50-SN-0(N,TOT),,SIG) 1081702000003 SAMPLE Sample contained in stainless steel holder 1081702000004 DETECTOR (SCIN) Bubble free NE-224 liquid scintillator with 1081702000005 aluminum cell used as main detector. Monitor detector 1081702000006 is 18.4-cm diameter by 5.08-cm thick NE-224 liquid 1081702000007 scintillator with layers of mu-metal to shield 1081702000008 detector from magnetic fields 1081702000009 INC-SPECT Energy and energy spread of incident neutrons 1081702000010 determined from total cross sections of carbon. 1081702000011 METHOD (TRN) Transmission measurement. Detector shadowed 1081702000012 from neutron source by sample. Sample-source distance 1081702000013 is 60-cm. 1081702000014 CORRECTION Data corrected for in-scattering. 1081702000015 ERR-ANALYS (DATA-ERR) Sources of uncertainty include- 1081702000016 -statistics 1081702000017 -in-scattering 1081702000018 -hardening effects 1081702000019 all sources contribute less than 1% each. 1081702000020 HISTORY (19860313C) 1081702000021 (20110727A) SD: BIB section updated. 1081702000022 ENDBIB 20 0 1081702000023 NOCOMMON 0 0 1081702000024 DATA 3 21 1081702000025 EN DATA DATA-ERR 1081702000026 MEV B PER-CENT 1081702000027 5.049 4.07 1.0 1081702000028 5.252 4.01 1.0 1081702000029 5.457 4.02 1.0 1081702000030 5.864 4.12 1.0 1081702000031 6.068 4.08 1.0 1081702000032 6.170 4.17 1.0 1081702000033 6.474 4.14 1.0 1081702000034 6.775 4.09 1.0 1081702000035 6.878 4.13 1.0 1081702000036 7.080 4.03 1.0 1081702000037 7.285 4.16 1.0 1081702000038 7.488 4.18 1.2 1081702000039 7.680 4.44 1.1 1081702000040 7.917 4.36 1.2 1081702000041 8.130 4.27 1.2 1081702000042 20.00 3.92 2.0 1081702000043 21.00 3.95 2.0 1081702000044 22.00 3.85 2.0 1081702000045 23.00 3.72 2.0 1081702000046 24.00 3.51 2.0 1081702000047 26.00 3.54 2.0 1081702000048 ENDDATA 23 0 1081702000049 ENDSUBENT 48 0 1081702099999 ENDENTRY 20 0 1081799999999