ENTRY 21934 20170212 22592193400000001 SUBENT 21934001 20170212 22592193400100001 BIB 15 203 2193400100002 INSTITUTE (2GERJUL) Inst.F.Chemie 1. 2193400100003 REFERENCE (J,NP/A,423,130,198401) 2193400100004 AUTHOR (R.Woelfle, S.Khatun, S.M.Qaim) 2193400100005 TITLE Triton-emission cross sections with 30 MeV 2193400100006 D(Be) break-up neutrons. 2193400100007 FACILITY (ISOCY,2GERJUL) Juelich Isochronous Cyclotron (Julic). 2193400100008 INC-SOURCE (D-BE ) 30 MeV deuterons on a 1 cm thick Be target. 2193400100009 .The integrated neutron flux in the zero degrees 2193400100010 direction over the energy range of 2 to 30 MeV 2193400100011 was about 1.5e+11*(1/sr*micro-Amp*sec) 2193400100012 INC-SPECT .30 MeV D(Be) break-up neutron spectrum. 2193400100013 .Spectrum characterization was performed using 2193400100014 the multiple-foil activation technique in 2193400100015 combination with the unfolding code SAND-II. 2193400100016 14 threshold reactions, with maxima of the 2193400100017 excitation functions between 4.5 and 25.0 MeV, 2193400100018 were used.Details given in Table 1, main ref. 2193400100019 -Spectrum digitized from Fig.1 of NP/A,423,130,1984 : 2193400100020 units En- Mev, Intensity - 10**10 n/(sr*muA*MeV) 2193400100021 En Intensity En Intensity 2193400100022 1.9927 1.6976 14.132 0.86138 2193400100023 2.2064 1.5490 14.600 0.84441 2193400100024 2.3347 1.4428 15.154 0.82320 2193400100025 2.4630 1.3281 15.708 0.79774 2193400100026 2.5913 1.2219 16.091 0.77651 2193400100027 2.7194 1.1369 16.347 0.74254 2193400100028 2.8476 1.0520 16.687 0.70008 2193400100029 3.0184 0.95852 17.028 0.64063 2193400100030 3.3168 0.88207 17.369 0.58967 2193400100031 3.6152 0.81412 17.710 0.53871 2193400100032 3.8711 0.72917 18.051 0.49200 2193400100033 4.1695 0.66547 18.435 0.44104 2193400100034 4.6380 0.64000 18.818 0.39008 2193400100035 5.1916 0.62304 19.287 0.34762 2193400100036 5.5749 0.59332 19.713 0.30941 2193400100037 6.0008 0.57635 20.138 0.27970 2193400100038 6.2989 0.57212 20.607 0.24574 2193400100039 6.7671 0.59763 21.118 0.21603 2193400100040 7.1502 0.62738 21.672 0.19057 2193400100041 7.4907 0.64439 22.183 0.16511 2193400100042 8.0017 0.64867 22.822 0.14390 2193400100043 8.6404 0.64445 23.375 0.12693 2193400100044 9.0661 0.64872 23.971 0.10997 2193400100045 9.3215 0.66148 24.610 0.93011E-01 2193400100046 9.7898 0.68699 25.249 0.76051E-01 2193400100047 10.215 0.72100 25.845 0.67585E-01 2193400100048 10.556 0.76349 26.569 0.50629E-01 2193400100049 10.854 0.80174 27.250 0.42167E-01 2193400100050 11.194 0.83149 27.889 0.33703E-01 2193400100051 11.662 0.85276 28.613 0.20996E-01 2193400100052 12.258 0.86553 29.294 0.16782E-01 2193400100053 12.855 0.87406 29.933 0.12566E-01 2193400100054 13.493 0.86984 2193400100055 Upper limit Lower limit 2193400100056 2.1612 2.0715 2.0384 1.0902 2193400100057 2.3319 1.9823 2.2944 0.99247 2193400100058 2.4602 1.8761 2.5503 0.90752 2193400100059 2.5458 1.7869 2.7636 0.82257 2193400100060 2.5890 1.6722 3.0620 0.74188 2193400100061 2.6747 1.5532 3.4031 0.65268 2193400100062 2.8031 1.4385 3.7015 0.58898 2193400100063 2.9314 1.3154 4.0424 0.53377 2193400100064 3.0595 1.2431 4.5110 0.49556 2193400100065 3.4005 1.1794 4.8943 0.47859 2193400100066 3.6137 1.1157 5.1924 0.47011 2193400100067 3.7419 1.0223 5.4052 0.48286 2193400100068 3.8701 0.93308 5.5329 0.48287 2193400100069 4.0833 0.86512 5.7885 0.47014 2193400100070 4.3815 0.83540 6.0866 0.46166 2193400100071 4.8074 0.81843 6.3846 0.47017 2193400100072 5.0203 0.81419 6.7676 0.49992 2193400100073 5.4037 0.78447 7.1933 0.51694 2193400100074 5.6594 0.74201 7.5764 0.53395 2193400100075 5.8724 0.72078 7.9170 0.54246 2193400100076 6.2556 0.71655 8.1725 0.54248 2193400100077 6.5535 0.73356 8.6409 0.53825 2193400100078 6.8942 0.73782 9.1944 0.53828 2193400100079 7.3623 0.77608 9.4499 0.54679 2193400100080 7.7029 0.78034 9.7478 0.57229 2193400100081 8.2139 0.78037 10.131 0.61054 2193400100082 8.8100 0.77615 10.556 0.66154 2193400100083 9.2357 0.79316 10.897 0.71253 2193400100084 9.5762 0.83141 11.237 0.74229 2193400100085 10.002 0.83568 11.663 0.77204 2193400100086 10.598 0.89094 12.003 0.79330 2193400100087 11.066 0.93769 12.386 0.80606 2193400100088 11.321 0.94620 12.855 0.81458 2193400100089 11.875 0.94622 13.323 0.81461 2193400100090 12.556 0.94626 13.664 0.80188 2193400100091 13.323 0.93780 13.962 0.77216 2193400100092 14.089 0.93359 14.260 0.75943 2193400100093 14.643 0.92512 14.558 0.75520 2193400100094 15.196 0.92090 14.942 0.74247 2193400100095 15.665 0.91243 15.325 0.73400 2193400100096 16.005 0.88271 15.751 0.71703 2193400100097 16.304 0.83175 16.134 0.69580 2193400100098 16.730 0.76380 16.347 0.66608 2193400100099 17.156 0.68736 16.645 0.62361 2193400100100 17.497 0.62790 16.986 0.56841 2193400100101 17.966 0.55996 17.284 0.53019 2193400100102 18.349 0.49201 17.583 0.49622 2193400100103 18.860 0.42407 17.923 0.46650 2193400100104 19.329 0.37736 18.307 0.41554 2193400100105 19.755 0.33490 18.776 0.36459 2193400100106 20.181 0.30519 19.244 0.32213 2193400100107 20.607 0.26273 19.713 0.27968 2193400100108 21.161 0.23302 20.139 0.24996 2193400100109 21.629 0.20756 20.607 0.22025 2193400100110 22.183 0.18210 21.118 0.19479 2193400100111 22.779 0.16514 21.672 0.16508 2193400100112 23.375 0.14393 22.183 0.14387 2193400100113 24.014 0.12272 22.822 0.12266 2193400100114 24.610 0.10576 23.375 0.10569 2193400100115 25.249 0.88795E-01 24.014 0.88733E-01 2193400100116 25.888 0.76083E-01 24.610 0.71771E-01 2193400100117 26.569 0.63373E-01 25.249 0.63307E-01 2193400100118 27.250 0.50663E-01 25.888 0.46347E-01 2193400100119 27.889 0.42200E-01 26.612 0.37887E-01 2193400100120 28.613 0.29492E-01 27.250 0.25175E-01 2193400100121 29.294 0.21030E-01 27.889 0.16711E-01 2193400100122 29.890 0.16812E-01 28.570 0.12498E-01 2193400100123 29.294 0.12534E-01 2193400100124 29.933 0.83181E-02 2193400100125 Upper/lower limits gives errors limits assuming errors 2193400100126 - CS of monitor threshold reactions - 10%, 2193400100127 - absolute activity of activation products - 10%; 2193400100128 were calculated Monte Carlo programme. 2193400100129 Integrated neutron flux in 0 deg direction over 2193400100130 2-30 MeV energy range amounts to 1.5E+11 1/(sr*muA*sec)2193400100131 SAMPLE .Natural targets 2193400100132 .High-purity metal sheets (1 cm diameter and about 2193400100133 0.8 cm length ) and Al monitor foils were stacked 2193400100134 together . 2193400100135 METHOD (CHSEP,BCINT) Chemical separation of tritium. 2193400100136 .High-purity metal sheets and Al-monitor foils 2193400100137 were stacked together and irradiated for 2193400100138 several hours at distances about 3 cm from 2193400100139 the Be-converter 2193400100140 DETECTOR (PROPC) Low-level gas-phase beta(-) counter 2193400100141 (GELI) For gamma-ray spectroscopy of irradiated monitor2193400100142 foils. 2193400100143 MONITOR ((MONIT)13-AL-27(N,A)11-NA-24,,SIG,,SPA) 2193400100144 For spectrum shape 2193400100145 (49-IN-115(N,INL)49-IN-115-M,,SIG) 2193400100146 Max.response region 1.5 - 11.5 MeV 2193400100147 (28-NI-58(N,P)27-CO-58-G,,SIG) 2193400100148 Max.response region 4. - 14.5 MeV 2193400100149 (26-FE-54(N,P)25-MN-54,,SIG) 2193400100150 Max.response region 4.5 - 14.5 MeV 2193400100151 (22-TI-46(N,P)21-SC-46,,SIG) 2193400100152 Max.response region 6.5 - 22. MeV 2193400100153 (13-AL-27(N,A)11-NA-24-G,,SIG) 2193400100154 Max.response region 9. - 17.5 MeV 2193400100155 (26-FE-56(N,P)25-MN-56,,SIG) 2193400100156 Max.response region 9. - 18. MeV 2193400100157 (29-CU-65(N,P)28-NI-65,,SIG) 2193400100158 Max.response region 9. - 25. MeV 2193400100159 (41-NB-93(N,2N)41-NB-92-M,,SIG) 2193400100160 Max.response region 11. - 23.5 MeV 2193400100161 (22-TI-48(N,P)21-SC-48,,SIG) 2193400100162 Max.response region 11. - 26. MeV 2193400100163 (27-CO-59(N,2N)27-CO-58-G,,SIG) 2193400100164 Max.response region 13. - 27.5 MeV 2193400100165 (39-Y-89(N,2N)39-Y-88-G,,SIG) 2193400100166 Max.response region 13.5 - 27.5 MeV 2193400100167 (21-SC-45(N,2N)21-SC-44-M,,SIG) 2193400100168 Max.response region 14. - 28. MeV 2193400100169 (40-ZR-90(N,2N)40-ZR-89-G,,SIG) 2193400100170 Max.response region 14.5 - 29.5 MeV 2193400100171 (79-AU-197(N,3N)79-AU-195,,SIG) 2193400100172 Max.response region 19.5 - 20. MeV 2193400100173 Max.response region - region where 2193400100174 SIG(E) > or = 0.5*SIGmaximal . 2193400100175 Threshold monitor reactions were used for neutron 2193400100176 spectrum unfolding. 2193400100177 MONIT-REF (,,3,ENDF/B-IV,,1975) Dosimetry file. See also: 2193400100178 (,B.A.Magurno,R,BNL-NCS-50446,1975) 2193400100179 For In-115,Ni-58,Fe-54,Fe-56,Ti-46,Ti-48,Nb-93,Co-59, 2193400100180 monitors 2193400100181 (,B.P.Bayhurst+,J,PR/C,12,451,1975) 2193400100182 For Al-27,Y-89,Sc-45,Zr-90,Au-197 monitors 2193400100183 (,D.I.Garber+,R,BNL-325,1976) 2193400100184 Neutron cross sections, vol.II . 2193400100185 For Cu-65 monitor 2193400100186 RAD-DET (1-H-3,B-) 2193400100187 ERR-ANALYS (ERR-T) Total error, about 30 percent. 2193400100188 .Sources of systematic errors were uncertainties in 2193400100189 (ERR-1) Quantitative isolation of tritium ( 3 % ) 2193400100190 (ERR-2) Contribution of tritium from impurities in 2193400100191 the target material, especially Li ( 2 % ) 2193400100192 (ERR-3) Efficiency of beta(-) detector ( 2 % ) 2193400100193 (ERR-4,,10.) Estimation of triton recoil losses (<10%) 2193400100194 (ERR-5) Determination of neutron flux ( 20 % ) 2193400100195 Statistical and systematic errors were combined in 2193400100196 quadrature. 2193400100197 HISTORY (19840809C) BN. 2193400100198 (19850311E) 2193400100199 (20170212A) M.M. Spectrum information was added. 2193400100200 Upper -> lower case correction. 2193400100201 Dates were corrected for 4-digits year. 2193400100202 Article was checked, BIB information was updated in 2193400100203 INC-SPECT,MONITOR,MONIT-REF,STATUS,ERR-ANALYS, 2193400100204 DETECTOR 2193400100205 ENDBIB 203 0 2193400100206 COMMON 7 6 2193400100207 EN-DUMMY MONIT MONIT-ERR ERR-1 ERR-2 ERR-3 2193400100208 ERR-5 2193400100209 MEV MB MB PER-CENT PER-CENT PER-CENT 2193400100210 PER-CENT 2193400100211 12. 55. 12. 3. 2. 2. 2193400100212 20. 2193400100213 ENDCOMMON 6 0 2193400100214 ENDSUBENT 213 0 2193400199999 SUBENT 21934002 20170212 22592193400200001 BIB 4 6 2193400200002 REACTION (13-AL-27(N,X)1-H-3,,SIG,,SPA) 2193400200003 30 MeV D(Be) break-up neutron spectrum 2193400200004 SAMPLE Natural Al, weight 1.59 g, purity 99.99 % . 2193400200005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193400200006 HISTORY (19840809C) 2193400200007 (19850311E) 2193400200008 ENDBIB 6 0 2193400200009 NOCOMMON 0 0 2193400200010 DATA 2 1 2193400200011 DATA ERR-T 2193400200012 MB MB 2193400200013 1.4000E+00 4.2000E-01 2193400200014 ENDDATA 3 0 2193400200015 ENDSUBENT 14 0 2193400299999 SUBENT 21934003 20170212 22592193400300001 BIB 4 6 2193400300002 REACTION (22-TI-0(N,X)1-H-3,,SIG,,SPA) 2193400300003 30 MeV D(Be) break-up neutron spectrum 2193400300004 SAMPLE Natural Ti, weight 2.13 g, purity 99.9 % . 2193400300005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193400300006 HISTORY (19840809C) 2193400300007 (19850311E) 2193400300008 ENDBIB 6 0 2193400300009 NOCOMMON 0 0 2193400300010 DATA 2 1 2193400300011 DATA ERR-T 2193400300012 MB MB 2193400300013 4.8000E-01 1.4000E-01 2193400300014 ENDDATA 3 0 2193400300015 ENDSUBENT 14 0 2193400399999 SUBENT 21934004 20170212 22592193400400001 BIB 4 6 2193400400002 REACTION (23-V-51(N,X)1-H-3,,SIG,,SPA) 2193400400003 30 MeV D(Be) break-up neutron spectrum 2193400400004 SAMPLE Natural V, weight 2.40 g, purity 99.8 % . 2193400400005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193400400006 HISTORY (19840809C) 2193400400007 (19850311E) 2193400400008 ENDBIB 6 0 2193400400009 NOCOMMON 0 0 2193400400010 DATA 2 1 2193400400011 DATA ERR-T 2193400400012 MB MB 2193400400013 5.0000E-01 1.5000E-01 2193400400014 ENDDATA 3 0 2193400400015 ENDSUBENT 14 0 2193400499999 SUBENT 21934005 20170212 22592193400500001 BIB 4 6 2193400500002 REACTION (24-CR-0(N,X)1-H-3,,SIG,,SPA) 2193400500003 30 MeV D(Be) break-up neutron spectrum 2193400500004 SAMPLE Natural Cr, weight 4.38 g, purity 99.99 % . 2193400500005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193400500006 HISTORY (19840809C) 2193400500007 (19850311E) 2193400500008 ENDBIB 6 0 2193400500009 NOCOMMON 0 0 2193400500010 DATA 2 1 2193400500011 DATA ERR-T 2193400500012 MB MB 2193400500013 4.0000E-01 1.2000E-01 2193400500014 ENDDATA 3 0 2193400500015 ENDSUBENT 14 0 2193400599999 SUBENT 21934006 20170212 22592193400600001 BIB 4 6 2193400600002 REACTION (25-MN-55(N,X)1-H-3,,SIG,,SPA) 2193400600003 30 MeV D(Be) break-up neutron spectrum 2193400600004 SAMPLE Natural Mn, weight 4.81 g, purity 99.98 % . 2193400600005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193400600006 HISTORY (19840809C) 2193400600007 (19850311E) 2193400600008 ENDBIB 6 0 2193400600009 NOCOMMON 0 0 2193400600010 DATA 2 1 2193400600011 DATA ERR-T 2193400600012 MB MB 2193400600013 6.4000E-01 2.0000E-01 2193400600014 ENDDATA 3 0 2193400600015 ENDSUBENT 14 0 2193400699999 SUBENT 21934007 20170212 22592193400700001 BIB 4 6 2193400700002 REACTION (26-FE-0(N,X)1-H-3,,SIG,,SPA) 2193400700003 30 MeV D(Be) break-up neutron spectrum 2193400700004 SAMPLE Natural Fe, weight 3.10 g, purity 99.99 % . 2193400700005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193400700006 HISTORY (19840809C) 2193400700007 (19850311E) 2193400700008 ENDBIB 6 0 2193400700009 NOCOMMON 0 0 2193400700010 DATA 2 1 2193400700011 DATA ERR-T 2193400700012 MB MB 2193400700013 4.0000E-01 1.2000E-01 2193400700014 ENDDATA 3 0 2193400700015 ENDSUBENT 14 0 2193400799999 SUBENT 21934008 20170212 22592193400800001 BIB 4 6 2193400800002 REACTION (27-CO-59(N,X)1-H-3,,SIG,,SPA) 2193400800003 30 MeV D(Be) break-up neutron spectrum 2193400800004 SAMPLE Natural CO, weight 3.55 g, purity 99.998 % . 2193400800005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193400800006 HISTORY (19840809C) 2193400800007 (19850311E) 2193400800008 ENDBIB 6 0 2193400800009 NOCOMMON 0 0 2193400800010 DATA 2 1 2193400800011 DATA ERR-T 2193400800012 MB MB 2193400800013 6.4000E-01 2.0000E-01 2193400800014 ENDDATA 3 0 2193400800015 ENDSUBENT 14 0 2193400899999 SUBENT 21934009 20170212 22592193400900001 BIB 4 6 2193400900002 REACTION (28-NI-0(N,X)1-H-3,,SIG,,SPA) 2193400900003 30 MeV D(Be) break-up neutron spectrum 2193400900004 SAMPLE Natural Ni, weight 3.57 g, purity 99.997 % . 2193400900005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193400900006 HISTORY (19840809C) 2193400900007 (19850311E) 2193400900008 ENDBIB 6 0 2193400900009 NOCOMMON 0 0 2193400900010 DATA 2 1 2193400900011 DATA ERR-T 2193400900012 MB MB 2193400900013 3.8000E-01 1.4000E-01 2193400900014 ENDDATA 3 0 2193400900015 ENDSUBENT 14 0 2193400999999 SUBENT 21934010 20170212 22592193401000001 BIB 4 6 2193401000002 REACTION (29-CU-0(N,X)1-H-3,,SIG,,SPA) 2193401000003 30 MeV D(Be) break-up neutron spectrum 2193401000004 SAMPLE Natural Cu, weight 5.55 g, purity 99.999 % . 2193401000005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193401000006 HISTORY (19840809C) 2193401000007 (19850311E) 2193401000008 ENDBIB 6 0 2193401000009 NOCOMMON 0 0 2193401000010 DATA 2 1 2193401000011 DATA ERR-T 2193401000012 MB MB 2193401000013 7.8000E-01 2.5000E-01 2193401000014 ENDDATA 3 0 2193401000015 ENDSUBENT 14 0 2193401099999 SUBENT 21934011 20170212 22592193401100001 BIB 4 6 2193401100002 REACTION (41-NB-93(N,X)1-H-3,,SIG,,SPA) 2193401100003 30 MeV D(Be) break-up neutron spectrum 2193401100004 SAMPLE Natural Nb, weight 5.36 g, purity 99.5 % . 2193401100005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193401100006 HISTORY (19840809C) 2193401100007 (19850311E) 2193401100008 ENDBIB 6 0 2193401100009 NOCOMMON 0 0 2193401100010 DATA 2 1 2193401100011 DATA ERR-T 2193401100012 MB MB 2193401100013 6.1000E-01 2.0000E-01 2193401100014 ENDDATA 3 0 2193401100015 ENDSUBENT 14 0 2193401199999 SUBENT 21934012 20170212 22592193401200001 BIB 4 6 2193401200002 REACTION (42-MO-0(N,X)1-H-3,,SIG,,SPA) 2193401200003 30 MeV D(Be) break-up neutron spectrum 2193401200004 SAMPLE Natural Mo, weight 3.99 g, purity 99.99 % . 2193401200005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193401200006 HISTORY (19840809C) 2193401200007 (19850311E) 2193401200008 ENDBIB 6 0 2193401200009 NOCOMMON 0 0 2193401200010 DATA 2 1 2193401200011 DATA ERR-T 2193401200012 MB MB 2193401200013 6.2000E-01 2.0000E-01 2193401200014 ENDDATA 3 0 2193401200015 ENDSUBENT 14 0 2193401299999 SUBENT 21934013 20170212 22592193401300001 BIB 4 6 2193401300002 REACTION (47-AG-0(N,X)1-H-3,,SIG,,SPA) 2193401300003 30 MeV D(Be) break-up neutron spectrum 2193401300004 SAMPLE Natural Ag, weight 4.80 g, purity 99.998 % . 2193401300005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193401300006 HISTORY (19840809C) 2193401300007 (19850311E) 2193401300008 ENDBIB 6 0 2193401300009 NOCOMMON 0 0 2193401300010 DATA 2 1 2193401300011 DATA ERR-T 2193401300012 MB MB 2193401300013 4.7000E-01 1.5000E-01 2193401300014 ENDDATA 3 0 2193401300015 ENDSUBENT 14 0 2193401399999 SUBENT 21934014 20170212 22592193401400001 BIB 4 6 2193401400002 REACTION (73-TA-181(N,X)1-H-3,,SIG,,SPA) 2193401400003 30 MeV D(Be) break-up neutron spectrum 2193401400004 SAMPLE Natural Ta, weight 8.73 g, purity > 99.9 % . 2193401400005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193401400006 HISTORY (19840809C) 2193401400007 (19850311E) 2193401400008 ENDBIB 6 0 2193401400009 NOCOMMON 0 0 2193401400010 DATA 2 1 2193401400011 DATA ERR-T 2193401400012 MB MB 2193401400013 5.9000E-01 2.4000E-01 2193401400014 ENDDATA 3 0 2193401400015 ENDSUBENT 14 0 2193401499999 SUBENT 21934015 20170212 22592193401500001 BIB 4 6 2193401500002 REACTION (81-TL-0(N,X)1-H-3,,SIG,,SPA) 2193401500003 30 MeV D(Be) break-up neutron spectrum 2193401500004 SAMPLE Natural Tl, weight 6.72 g, purity 99.999 % . 2193401500005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193401500006 HISTORY (19840809C) 2193401500007 (19850311E) 2193401500008 ENDBIB 6 0 2193401500009 NOCOMMON 0 0 2193401500010 DATA 2 1 2193401500011 DATA ERR-T 2193401500012 MB MB 2193401500013 7.6000E-01 3.5000E-01 2193401500014 ENDDATA 3 0 2193401500015 ENDSUBENT 14 0 2193401599999 SUBENT 21934016 20170212 22592193401600001 BIB 4 6 2193401600002 REACTION (82-PB-0(N,X)1-H-3,,SIG,,SPA) 2193401600003 30 MeV D(Be) break-up neutron spectrum 2193401600004 SAMPLE Natural Pb, weight 6.01 g, purity 99.99 % . 2193401600005 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193401600006 HISTORY (19840809C) 2193401600007 (19850311E) 2193401600008 ENDBIB 6 0 2193401600009 NOCOMMON 0 0 2193401600010 DATA 2 1 2193401600011 DATA ERR-T 2193401600012 MB MB 2193401600013 6.6000E-01 2.0000E-01 2193401600014 ENDDATA 3 0 2193401600015 ENDSUBENT 14 0 2193401699999 SUBENT 21934017 20170212 22592193401700001 BIB 4 7 2193401700002 REACTION (83-BI-209(N,X)1-H-3,,SIG,,SPA) 2193401700003 30 MeV D(Be) break-up neutron spectrum 2193401700004 SAMPLE Natural Bi, weight 8.48 g, purity 99.99 % . 2193401700005 Used in form of an ingot. 2193401700006 STATUS (TABLE) Table 2 of J,NP/A,423,130,1984 2193401700007 HISTORY (19840809C) 2193401700008 (19850311E) 2193401700009 ENDBIB 7 0 2193401700010 NOCOMMON 0 0 2193401700011 DATA 2 1 2193401700012 DATA ERR-T 2193401700013 MB MB 2193401700014 7.8000E-01 2.5000E-01 2193401700015 ENDDATA 3 0 2193401700016 ENDSUBENT 15 0 2193401799999 ENDENTRY 17 0 2193499999999