ENTRY 23295 20211202 23052329500000001 SUBENT 23295001 20211202 23052329500100001 BIB 7 25 2329500100002 TITLE Accelerator mass spectrometry measurements of the 2329500100003 13C(n,gamma)14C and 14N(n,p)14C cross sections. 2329500100004 AUTHOR (A.Wallner,M.Bichler,K.Buczak,I.Dillmann,F.Kaeppeler, 2329500100005 A.Karakas,C.Lederer,M.Lugaro,K.Mair,A.Mengoni, 2329500100006 G.Schaetzel,P.Steier,H.P.Trautvetter) 2329500100007 INSTITUTE (2GERKFK) I.Dillmann,F.Kaeppeler, 2329500100008 (2AUSVIE) VERA Lab. K.Buczak,C.Lederer,K.Mair, 2329500100009 G.Schaetzel,P.Steier 2329500100010 (3AULCBR) A.Wallner,A.Karakas, 2329500100011 (2AUSATI) M.Bichler, 2329500100012 (3HUNHUN) Konkoly Observatory, Hungarian Academy of 2329500100013 Sciences, Hungary. M.Lugaro, 2329500100014 (2ZZZCER) A.Mengoni, 2329500100015 (2GERBOC) H.P.Trautvetter 2329500100016 REFERENCE (J,PR/C,93,045803,2016) 2329500100017 #doi:10.1103/PhysRevC.93.045803 2329500100018 And Supplementary Material: 2329500100019 http://link.aps.org/supplemental/10.1103/ 2329500100020 PhysRevC.93.045803 2329500100021 METHOD (AMS) 2329500100022 ERR-ANALYS Statistical uncertainties are negligible in final data2329500100023 of AMS. 2329500100024 HISTORY (20160421C) M.M. 2329500100025 (20211202U) SD: METHOD was added. FACILITY deleted 2329500100026 (not for sample irradiation). 2329500100027 ENDBIB 25 0 2329500100028 NOCOMMON 0 0 2329500100029 ENDSUBENT 28 0 2329500199999 SUBENT 23295002 20160421 22492329500200001 BIB 12 80 2329500200002 REACTION (7-N-14(N,P)6-C-14,,SIG,,MXW) 2329500200003 INC-SOURCE (P-LI7) LI-7(p,n)Be-7 reaction. Proton energy 1912 keV.2329500200004 INC-SPECT Quasi-Maxwell-Boltzmann (q-MB) spectrum at kT=25 keV 2329500200005 Exp.spectrum is on Fig.4 upper of PR/C,93,045803,2016 2329500200006 Neutron fluence - 8.04*10**14 /cm2. 2329500200007 Relative neutron spectrum: 2329500200008 En,keV N(E) En,keV N(E) En,keV N(E) 2329500200009 0. 0.0007 37. 0.0146 74. 0.0082 2329500200010 1. 0.0026 38. 0.0145 75. 0.0079 2329500200011 2. 0.0037 39. 0.0144 76. 0.0076 2329500200012 3. 0.0048 40. 0.0143 77. 0.0074 2329500200013 4. 0.0056 41. 0.0142 78. 0.0072 2329500200014 5. 0.0064 42. 0.0141 79. 0.0069 2329500200015 6. 0.0071 43. 0.0139 80. 0.0067 2329500200016 7. 0.0077 44. 0.0138 81. 0.0065 2329500200017 8. 0.0083 45. 0.0137 82. 0.0062 2329500200018 9. 0.0090 46. 0.0135 83. 0.0060 2329500200019 10. 0.0095 47. 0.0133 84. 0.0057 2329500200020 11. 0.0100 48. 0.0132 85. 0.0055 2329500200021 12. 0.0103 49. 0.0130 86. 0.0052 2329500200022 13. 0.0107 50. 0.0129 87. 0.0050 2329500200023 14. 0.0111 51. 0.0128 88. 0.0048 2329500200024 15. 0.0115 52. 0.0126 89. 0.0045 2329500200025 16. 0.0118 53. 0.0125 90. 0.0043 2329500200026 17. 0.0122 54. 0.0123 91. 0.0040 2329500200027 18. 0.0125 55. 0.0122 92. 0.0038 2329500200028 19. 0.0129 56. 0.0120 93. 0.0036 2329500200029 20. 0.0132 57. 0.0118 94. 0.0033 2329500200030 21. 0.0135 58. 0.0117 95. 0.0031 2329500200031 22. 0.0137 59. 0.0115 96. 0.0029 2329500200032 23. 0.0139 60. 0.0113 97. 0.0027 2329500200033 24. 0.0142 61. 0.0110 98. 0.0024 2329500200034 25. 0.0144 62. 0.0108 99. 0.0022 2329500200035 26. 0.0147 63. 0.0106 100. 0.0020 2329500200036 27. 0.0150 64. 0.0104 101. 0.0017 2329500200037 28. 0.0152 65. 0.0101 102. 0.0015 2329500200038 29. 0.0154 66. 0.0099 103. 0.0012 2329500200039 30. 0.0154 67. 0.0097 104. 0.0010 2329500200040 31. 0.0152 68. 0.0095 105. 0.0008 2329500200041 32. 0.0151 69. 0.0092 106. 0.0005 2329500200042 33. 0.0150 70. 0.0091 107. 0.0003 2329500200043 34. 0.0149 71. 0.0089 108. 0.0001 2329500200044 35. 0.0148 72. 0.0086 2329500200045 36. 0.0147 73. 0.0084 2329500200046 FACILITY (VDG,2GERKFK) 3.7 MV Van de Graaff 2329500200047 SAMPLE The uracil (C4H4N2O2) powder was pressed into pellets 2329500200048 and sandwiched between Au foils. 2329500200049 MONITOR (79-AU-197(N,G)79-AU-198,,SIG,,SPA) 2329500200050 Spectrum average value. 2329500200051 Used as monitor to determine the neutron fluence. 2329500200052 DECAY-MON (79-AU-198,,DG,411.8) 2329500200053 DETECTOR (HPGE) HPGe well-calibrated to measure the induced Au 2329500200054 activity. 2329500200055 ANALYSIS Exp. cross-section SIG was defined as : 2329500200056 SIG=(14C/14N)*(1/F), where 2329500200057 F- total neutron fluence, 2329500200058 14C/14N - isotope ratio measured via AMS ; 2329500200059 Because 12C is correlated with 14N atom number via 2329500200060 the stoichiometry of uracil compound C4H4N2O2, 2329500200061 ratio 14C/12C were measured, where 12C/14N=1.98 . 2329500200062 Ratio 14C/C12 for blank - (0.16+-0.05) *10**-13, 2329500200063 for kT=25 keV - (6.90+-0.35)*10**-13. 2329500200064 REL-REF (A,22719002,T.Sanami+,J,NIM/A,394,368,1997) 2329500200065 (D,22078001,K.Brehm+,J,ZP/A,330,167,1988) 2329500200066 (A,22345001,T.Shima+,J,NIM/A,356,347,1995) 2329500200067 (A,13164002,P.E.Koehler+,J,PR/C,39,1655,1989) 2329500200068 ERR-ANALYS (ERR-T) Total uncertainty - 6% . 2329500200069 - Neutron fluence uncertainty - 3%, 2329500200070 consist of 2329500200071 (ERR-1) Au cross section 1.5% 2329500200072 (ERR-2) Counting efficiency 2.0% 2329500200073 (ERR-3,,0.5) Gamma intensity per decay <0.5% 2329500200074 (ERR-4,,0.5) Time factors <0.5 2329500200075 - AMS measurement 2329500200076 (ERR-5) Flux anisotropy 3.0% 2329500200077 (ERR-6) 14C in sample material 3.0% 2329500200078 (ERR-7) 14C in blank samples 2.0% 2329500200079 STATUS (TABLE) Table III of PR/C,93,045803,2016 -data, 2329500200080 Table VI - uncertainties. 2329500200081 (COREL,23295003) data at 123keV and 178 keV. 2329500200082 ENDBIB 80 0 2329500200083 COMMON 5 3 2329500200084 ERR-1 ERR-2 ERR-5 ERR-6 ERR-7 2329500200085 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2329500200086 1.5 2.0 3.0 3.0 2.0 2329500200087 ENDCOMMON 3 0 2329500200088 DATA 5 1 2329500200089 KT DATA ERR-T MONIT MONIT-ERR 2329500200090 KEV MB MB MB MB 2329500200091 25. 1.74 0.10 632. 9. 2329500200092 ENDDATA 3 0 2329500200093 ENDSUBENT 92 0 2329500299999 SUBENT 23295003 20160421 22492329500300001 BIB 11 176 2329500300002 REACTION (7-N-14(N,P)6-C-14,,SIG,,SPA) 2329500300003 INC-SOURCE (P-LI7) LI-7(p,n)Be-7 reaction. 2329500300004 Proton energy 1960keV and 2000 keV. 2329500300005 INC-SPECT Energy spread +- 30 keV. 2329500300006 Exp.spectra are on Fig.4 lower of PR/C,93,045803,2016 2329500300007 Neutron fluence - 8.64*10**14 /cm2 and 6.04*10**14 /cm22329500300008 for 128 and 182 keV neutrons, respectively. 2329500300009 EN-MEAN=128 keV EN-MEAN=182 keV 2329500300010 En,keV N(E) En,keV N(E) 2329500300011 45. 0.0000 104. 0.0000 2329500300012 46. 0.0000 105. 0.0000 2329500300013 47. 0.0000 106. 0.0000 2329500300014 48. 0.0000 107. 0.0000 2329500300015 49. 0.0000 108. 0.0001 2329500300016 50. 0.0001 109. 0.0001 2329500300017 51. 0.0001 110. 0.0001 2329500300018 52. 0.0002 111. 0.0002 2329500300019 53. 0.0002 112. 0.0002 2329500300020 54. 0.0003 113. 0.0003 2329500300021 55. 0.0004 114. 0.0004 2329500300022 56. 0.0004 115. 0.0005 2329500300023 57. 0.0005 116. 0.0006 2329500300024 58. 0.0006 117. 0.0007 2329500300025 59. 0.0007 118. 0.0008 2329500300026 60. 0.0008 119. 0.0009 2329500300027 61. 0.0009 120. 0.0011 2329500300028 62. 0.0010 121. 0.0012 2329500300029 63. 0.0012 122. 0.0013 2329500300030 64. 0.0013 123. 0.0015 2329500300031 65. 0.0015 124. 0.0017 2329500300032 66. 0.0017 125. 0.0019 2329500300033 67. 0.0018 126. 0.0020 2329500300034 68. 0.0020 127. 0.0022 2329500300035 69. 0.0021 128. 0.0024 2329500300036 70. 0.0023 129. 0.0026 2329500300037 71. 0.0025 130. 0.0028 2329500300038 72. 0.0026 131. 0.0030 2329500300039 73. 0.0028 132. 0.0033 2329500300040 74. 0.0031 133. 0.0035 2329500300041 75. 0.0033 134. 0.0038 2329500300042 76. 0.0035 135. 0.0040 2329500300043 77. 0.0037 136. 0.0042 2329500300044 78. 0.0039 137. 0.0046 2329500300045 79. 0.0041 138. 0.0048 2329500300046 80. 0.0043 139. 0.0051 2329500300047 81. 0.0046 140. 0.0053 2329500300048 82. 0.0048 141. 0.0056 2329500300049 83. 0.0051 142. 0.0059 2329500300050 84. 0.0053 143. 0.0062 2329500300051 85. 0.0056 144. 0.0065 2329500300052 86. 0.0058 145. 0.0068 2329500300053 87. 0.0061 146. 0.0072 2329500300054 88. 0.0064 147. 0.0074 2329500300055 89. 0.0067 148. 0.0078 2329500300056 90. 0.0070 149. 0.0081 2329500300057 91. 0.0073 150. 0.0084 2329500300058 92. 0.0075 151. 0.0087 2329500300059 93. 0.0078 152. 0.0090 2329500300060 94. 0.0082 153. 0.0093 2329500300061 95. 0.0084 154. 0.0096 2329500300062 96. 0.0087 155. 0.0100 2329500300063 97. 0.0090 156. 0.0102 2329500300064 98. 0.0093 157. 0.0106 2329500300065 99. 0.0097 158. 0.0108 2329500300066 100. 0.0100 159. 0.0112 2329500300067 101. 0.0102 160. 0.0114 2329500300068 102. 0.0105 161. 0.0117 2329500300069 103. 0.0107 162. 0.0120 2329500300070 104. 0.0110 163. 0.0123 2329500300071 105. 0.0113 164. 0.0125 2329500300072 106. 0.0116 165. 0.0129 2329500300073 107. 0.0118 166. 0.0130 2329500300074 108. 0.0121 167. 0.0134 2329500300075 109. 0.0124 168. 0.0137 2329500300076 110. 0.0127 169. 0.0139 2329500300077 111. 0.0130 170. 0.0142 2329500300078 112. 0.0132 171. 0.0145 2329500300079 113. 0.0135 172. 0.0148 2329500300080 114. 0.0138 173. 0.0150 2329500300081 115. 0.0141 174. 0.0154 2329500300082 116. 0.0144 175. 0.0156 2329500300083 117. 0.0145 176. 0.0158 2329500300084 118. 0.0148 177. 0.0161 2329500300085 119. 0.0151 178. 0.0164 2329500300086 120. 0.0154 179. 0.0167 2329500300087 121. 0.0156 180. 0.0169 2329500300088 122. 0.0159 181. 0.0174 2329500300089 123. 0.0162 182. 0.0175 2329500300090 124. 0.0165 183. 0.0173 2329500300091 125. 0.0165 184. 0.0170 2329500300092 126. 0.0162 185. 0.0167 2329500300093 127. 0.0160 186. 0.0165 2329500300094 128. 0.0157 187. 0.0161 2329500300095 129. 0.0154 188. 0.0158 2329500300096 130. 0.0152 189. 0.0154 2329500300097 131. 0.0149 190. 0.0152 2329500300098 132. 0.0146 191. 0.0148 2329500300099 133. 0.0143 192. 0.0145 2329500300100 134. 0.0141 193. 0.0141 2329500300101 135. 0.0138 194. 0.0138 2329500300102 136. 0.0136 195. 0.0135 2329500300103 137. 0.0133 196. 0.0131 2329500300104 138. 0.0131 197. 0.0128 2329500300105 139. 0.0128 198. 0.0124 2329500300106 140. 0.0125 199. 0.0121 2329500300107 141. 0.0122 200. 0.0117 2329500300108 142. 0.0119 201. 0.0114 2329500300109 143. 0.0117 202. 0.0111 2329500300110 144. 0.0114 203. 0.0106 2329500300111 145. 0.0111 204. 0.0103 2329500300112 146. 0.0109 205. 0.0099 2329500300113 147. 0.0106 206. 0.0096 2329500300114 148. 0.0104 207. 0.0092 2329500300115 149. 0.0101 208. 0.0088 2329500300116 150. 0.0097 209. 0.0085 2329500300117 151. 0.0094 210. 0.0081 2329500300118 152. 0.0092 211. 0.0077 2329500300119 153. 0.0089 212. 0.0074 2329500300120 154. 0.0086 213. 0.0070 2329500300121 155. 0.0083 214. 0.0066 2329500300122 156. 0.0080 215. 0.0062 2329500300123 157. 0.0077 216. 0.0058 2329500300124 158. 0.0073 217. 0.0054 2329500300125 159. 0.0070 218. 0.0050 2329500300126 160. 0.0067 219. 0.0047 2329500300127 161. 0.0063 220. 0.0043 2329500300128 162. 0.0060 221. 0.0038 2329500300129 163. 0.0056 222. 0.0035 2329500300130 164. 0.0053 223. 0.0031 2329500300131 165. 0.0049 224. 0.0027 2329500300132 166. 0.0046 225. 0.0022 2329500300133 167. 0.0042 226. 0.0018 2329500300134 168. 0.0039 227. 0.0014 2329500300135 169. 0.0035 228. 0.0010 2329500300136 170. 0.0032 229. 0.0005 2329500300137 171. 0.0028 230. 0.0001 2329500300138 172. 0.0024 2329500300139 173. 0.0021 2329500300140 174. 0.0017 2329500300141 175. 0.0013 2329500300142 176. 0.0009 2329500300143 177. 0.0005 2329500300144 178. 0.0001 2329500300145 FACILITY (VDG,2GERKFK) 3.7 MV Van de Graaff 2329500300146 SAMPLE The uracil (C4H4N2O2) powder was pressed into pellets 2329500300147 and sandwiched between Au foils. 2329500300148 MONITOR (79-AU-197(N,G)79-AU-198,,SIG,,SPA) 2329500300149 Spectrum average value. 2329500300150 Used as monitor to determine the neutron fluence. 2329500300151 DECAY-MON (79-AU-198,,DG,411.8) 2329500300152 DETECTOR (HPGE) HPGe well-calibrated to measure the induced Au 2329500300153 activity. 2329500300154 ANALYSIS Exp. cross-section SIG was defined as : 2329500300155 SIG=(14C/14N)*(1/F), where 2329500300156 F- total neutron fluence, 2329500300157 14C/14N - isotope ratio measured via AMS ; 2329500300158 Because 12C is correlated with 14N atom number via 2329500300159 the stoichiometry of uracil compound C4H4N2O2, 2329500300160 ratio 14C/12C were measured, where 12C/14N=1.98 . 2329500300161 Ratio 14C/C12 for blank - (0.16+-0.05) *10**-13, 2329500300162 for En=123 keV - (3.73+-0.19)*10**-13 2329500300163 for En=178 keV - (2.51+-0.13)*10**-13 . 2329500300164 ERR-ANALYS (ERR-T) Total uncertainty - 6% . 2329500300165 - Neutron fluence uncertainty - 3%, 2329500300166 consist of 2329500300167 (ERR-1) Au cross section 1.5% 2329500300168 (ERR-2) Counting efficiency 2.0% 2329500300169 (ERR-3,,0.5) Gamma intensity per decay <0.5% 2329500300170 (ERR-4,,0.5) Time factors <0.5 2329500300171 - AMS measurement 2329500300172 (ERR-5) Flux anisotropy 3.0% 2329500300173 (ERR-6) 14C in sample material 3.0% 2329500300174 (ERR-7) 14C in blank samples 2.0% 2329500300175 STATUS (TABLE) Tables III of PR/C,93,045803,2016 - data, 2329500300176 Table VI - uncertainties. 2329500300177 (COREL,23295002) data at kT 25 keV. 2329500300178 ENDBIB 176 0 2329500300179 COMMON 6 3 2329500300180 EN-RSL-HW ERR-1 ERR-2 ERR-5 ERR-6 ERR-7 2329500300181 KEV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2329500300182 30. 2.0 2.0 3.0 3.0 2.0 2329500300183 ENDCOMMON 3 0 2329500300184 DATA 5 2 2329500300185 EN-MEAN DATA ERR-T MONIT MONIT-ERR 2329500300186 KEV MB MB MB MB 2329500300187 123. 0.88 0.05 299. 6. 2329500300188 178. 0.90 0.05 265. 5. 2329500300189 ENDDATA 4 0 2329500300190 ENDSUBENT 189 0 2329500399999 SUBENT 23295004 20160421 22492329500400001 BIB 13 112 2329500400002 REACTION (6-C-13(N,G)6-C-14,,SIG,,MXW) 2329500400003 INC-SOURCE (P-LI7) LI-7(p,n)Be-7 reaction. Proton energy 1912 keV.2329500400004 INC-SPECT Quasi-Maxwell-Boltzmann (q-MB) spectrum at kT=25 keV. 2329500400005 Exp.spectrum is on Fig.4 upper of PR/C,93,045803,2016. 2329500400006 Neutron fluence - 13.8*10**14 /cm2. 2329500400007 Relative neutron spectrum: 2329500400008 En,keV N(E) En,keV N(E) En,keV N(E) 2329500400009 0. 0.0007 37. 0.0147 74. 0.0076 2329500400010 1. 0.0028 38. 0.0145 75. 0.0073 2329500400011 2. 0.0042 39. 0.0144 76. 0.0071 2329500400012 3. 0.0055 40. 0.0142 77. 0.0068 2329500400013 4. 0.0065 41. 0.0141 78. 0.0066 2329500400014 5. 0.0074 42. 0.0140 79. 0.0064 2329500400015 6. 0.0083 43. 0.0138 80. 0.0062 2329500400016 7. 0.0089 44. 0.0136 81. 0.0059 2329500400017 8. 0.0096 45. 0.0135 82. 0.0057 2329500400018 9. 0.0102 46. 0.0133 83. 0.0055 2329500400019 10. 0.0108 47. 0.0131 84. 0.0052 2329500400020 11. 0.0112 48. 0.0129 85. 0.0050 2329500400021 12. 0.0116 49. 0.0127 86. 0.0047 2329500400022 13. 0.0120 50. 0.0126 87. 0.0045 2329500400023 14. 0.0123 51. 0.0124 88. 0.0043 2329500400024 15. 0.0127 52. 0.0122 89. 0.0041 2329500400025 16. 0.0130 53. 0.0121 90. 0.0039 2329500400026 17. 0.0133 54. 0.0119 91. 0.0036 2329500400027 18. 0.0136 55. 0.0117 92. 0.0034 2329500400028 19. 0.0138 56. 0.0116 93. 0.0032 2329500400029 20. 0.0141 57. 0.0113 94. 0.0030 2329500400030 21. 0.0143 58. 0.0112 95. 0.0028 2329500400031 22. 0.0145 59. 0.0110 96. 0.0026 2329500400032 23. 0.0146 60. 0.0108 97. 0.0024 2329500400033 24. 0.0149 61. 0.0105 98. 0.0022 2329500400034 25. 0.0150 62. 0.0103 99. 0.0019 2329500400035 26. 0.0152 63. 0.0100 100. 0.0017 2329500400036 27. 0.0154 64. 0.0098 101. 0.0015 2329500400037 28. 0.0156 65. 0.0095 102. 0.0013 2329500400038 29. 0.0157 66. 0.0094 103. 0.0011 2329500400039 30. 0.0157 67. 0.0091 104. 0.0009 2329500400040 31. 0.0155 68. 0.0089 105. 0.0007 2329500400041 32. 0.0153 69. 0.0087 106. 0.0005 2329500400042 33. 0.0152 70. 0.0085 107. 0.0003 2329500400043 34. 0.0151 71. 0.0083 108. 0.0000 2329500400044 35. 0.0149 72. 0.0080 2329500400045 36. 0.0148 73. 0.0078 2329500400046 FACILITY (VDG,2GERKFK) 3.7 MV Van de Graaff 2329500400047 SAMPLE 13C-enriched graphite powder enclosed in Al containers 2329500400048 of 6 mm diameter. Gold foils served as monitors for the2329500400049 neutron fluence; were attached to the 13C sample to 2329500400050 form a stack of 197Au -13C- 197Au. 2329500400051 Additional Measurement: 2329500400052 13C-enriched graphite (98% 13C) from AMT Ltd., Israel ;2329500400053 spurious contents of 14N in the sample material; 2329500400054 irradiated at thermal flux 4*10**1 /sec/cm2 at TRIGA 2329500400055 reactor (epithermal to thermal flux ratio 1.3%) 2329500400056 Irradiation of 2329500400057 Sample C13-1 C13-2 C13-3 2329500400058 Fluence,10**15 /cm2 0.241+-0.010 14.9+-0.7 130+-10 2329500400059 14C/13C, 10**-11at/at 0.25+-0.02 1.60+-0.10 13.5+-1.02329500400060 SIGprod,mb 10.4+-1.0 10.7+-0.9 10.4+-0.92329500400061 Mean value of sample production cross section (contains2329500400062 contribution from N-14(N,P)C-14) is 10.5+-0.6 mb 2329500400063 ( Table I of PR/C,93,045803,2016). 2329500400064 From the measured effective thermal cross section, 2329500400065 SIGprod (the sum of 14C production from 13C(n,gamma) 2329500400066 and 14N(n,p) ), the intrinsic 14N content in the 2329500400067 graphite samples was then determined using the 2329500400068 thermal cross section values for 13C(n,gamma) 1.37mb 2329500400069 and for 14N(n,p) 1860. mb. 2329500400070 MONITOR (79-AU-197(N,G)79-AU-198,,SIG,,SPA) 2329500400071 Spectrum average value. 2329500400072 Used as monitor to determine the neutron fluence. 2329500400073 DECAY-MON (79-AU-198-G,2.62D,DG,411.8) 2329500400074 DETECTOR (HPGE) HPGe well-calibrated to measure the induced Au 2329500400075 activity. 2329500400076 CORRECTION For self-absorption in Au sample. 2329500400077 For decay during irradiation of Au sample. 2329500400078 For amount of C-14 from the N-14 contamination of the 2329500400079 C-13-enriched samples. 2329500400080 ANALYSIS Exp. cross-section SIG was defined as : 2329500400081 SIG=SIGprod - SIG14N*(N14N/N13C), where 2329500400082 SIGprod - sample production cross section, directly 2329500400083 measured to be 15.2+-2.9 microbarn; 2329500400084 SIG14N - N-14(n,p) cross section, 2329500400085 N14N/N13C - isotope ratio : 2329500400086 - defined to be equal 0.0049+-0.0004 as 2329500400087 (SIGprod/SIG13C-1)*(SIG13C/SIG14N) using measured 2329500400088 SIGprod thermal cross section 10.5mb and thermal 2329500400089 cross section C-13(n,g) 1.37+-0.04mb from REL-REF of 2329500400090 Mughabghab, 2329500400091 - in agreement with value 0.005+-0.001 obtained as 2329500400092 direct AMS result. 2329500400093 Measured isotope ratio 14C/13C 2329500400094 for blank - (10+-2)*10**-15, 2329500400095 for kT=25 keV - (21+-4)*10**-15 2329500400096 REL-REF (D,22170001,S.Raman+,J,PR/C,41,458,1990) 2329500400097 20+-9 microbarn at ~ 40 keV. 2329500400098 (D,22345006,T.Shima+,J,NP/A,621,231C,1997) 2329500400099 Lower than previous data. 2329500400100 ERR-ANALYS (ERR-T) Total uncertainty - 48% . 2329500400101 - Neutron fluence uncertainty - 3%, 2329500400102 consist of 2329500400103 (ERR-1) Au cross section 1.5% 2329500400104 (ERR-2) Counting efficiency 2.0% 2329500400105 (ERR-3,,0.5) Gamma intensity per decay <0.5% 2329500400106 (ERR-4,,0.5) Time factors <0.5 2329500400107 - AMS measurement 2329500400108 (ERR-5) Flux anisotropy 3.0% 2329500400109 (ERR-6) 14N-induced background 43.% 2329500400110 (ERR-7) 14C in sample material 19.% 2329500400111 (ERR-8) 14C in blank samples 10.% 2329500400112 STATUS (TABLE) Table V of PR/C,93,045803,2016 - data, 2329500400113 Table VI - uncertainties. 2329500400114 ENDBIB 112 0 2329500400115 COMMON 6 3 2329500400116 ERR-1 ERR-2 ERR-5 ERR-6 ERR-7 ERR-8 2329500400117 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2329500400118 1.5 2.0 3.0 43. 19. 10. 2329500400119 ENDCOMMON 3 0 2329500400120 DATA 5 1 2329500400121 KT DATA ERR-T MONIT MONIT-ERR 2329500400122 KEV MICRO-B MICRO-B MB MB 2329500400123 25. 6.7 3.2 632. 9. 2329500400124 ENDDATA 3 0 2329500400125 ENDSUBENT 124 0 2329500499999 SUBENT 23295005 20160421 22492329500500001 BIB 12 199 2329500500002 REACTION (6-C-13(N,G)6-C-14,,SIG,,SPA) 2329500500003 INC-SOURCE (P-LI7) LI-7(p,n)Be-7 reaction. 2329500500004 Proton energy 1960keV and 2000 keV. 2329500500005 INC-SPECT Energy spread +- 30 keV. 2329500500006 Exp.spectra are on Fig.4 lower of PR/C,93,045803,2016 2329500500007 Neutron fluence - 6.65*10**14 /cm2 and 4.67*10**14 /cm22329500500008 for 123 and 178 keV neutrons, respectively. 2329500500009 Relative neutron spectrum: 2329500500010 EN-MEAN=128 keV EN-MEAN=182 keV 2329500500011 En,keV N(E) En,keV N(E) 2329500500012 56. 0.0000 113. 0.0000 2329500500013 57. 0.0000 114. 0.0000 2329500500014 58. 0.0000 115. 0.0000 2329500500015 59. 0.0000 116. 0.0000 2329500500016 60. 0.0001 117. 0.0001 2329500500017 61. 0.0001 118. 0.0001 2329500500018 62. 0.0001 119. 0.0002 2329500500019 63. 0.0002 120. 0.0002 2329500500020 64. 0.0002 121. 0.0003 2329500500021 65. 0.0003 122. 0.0004 2329500500022 66. 0.0004 123. 0.0005 2329500500023 67. 0.0005 124. 0.0006 2329500500024 68. 0.0006 125. 0.0007 2329500500025 69. 0.0007 126. 0.0008 2329500500026 70. 0.0008 127. 0.0009 2329500500027 71. 0.0009 128. 0.0011 2329500500028 72. 0.0010 129. 0.0012 2329500500029 73. 0.0012 130. 0.0014 2329500500030 74. 0.0014 131. 0.0016 2329500500031 75. 0.0015 132. 0.0018 2329500500032 76. 0.0017 133. 0.0019 2329500500033 77. 0.0018 134. 0.0022 2329500500034 78. 0.0020 135. 0.0024 2329500500035 79. 0.0022 136. 0.0026 2329500500036 80. 0.0024 137. 0.0028 2329500500037 81. 0.0026 138. 0.0031 2329500500038 82. 0.0028 139. 0.0033 2329500500039 83. 0.0031 140. 0.0035 2329500500040 84. 0.0033 141. 0.0038 2329500500041 85. 0.0036 142. 0.0041 2329500500042 86. 0.0038 143. 0.0044 2329500500043 87. 0.0040 144. 0.0047 2329500500044 88. 0.0043 145. 0.0050 2329500500045 89. 0.0046 146. 0.0053 2329500500046 90. 0.0049 147. 0.0056 2329500500047 91. 0.0052 148. 0.0059 2329500500048 92. 0.0054 149. 0.0063 2329500500049 93. 0.0057 150. 0.0066 2329500500050 94. 0.0061 151. 0.0069 2329500500051 95. 0.0064 152. 0.0073 2329500500052 96. 0.0067 153. 0.0077 2329500500053 97. 0.0070 154. 0.0081 2329500500054 98. 0.0074 155. 0.0085 2329500500055 99. 0.0077 156. 0.0088 2329500500056 100. 0.0081 157. 0.0093 2329500500057 101. 0.0085 158. 0.0096 2329500500058 102. 0.0088 159. 0.0100 2329500500059 103. 0.0092 160. 0.0104 2329500500060 104. 0.0096 161. 0.0108 2329500500061 105. 0.0100 162. 0.0112 2329500500062 106. 0.0104 163. 0.0116 2329500500063 107. 0.0107 164. 0.0119 2329500500064 108. 0.0111 165. 0.0124 2329500500065 109. 0.0116 166. 0.0127 2329500500066 110. 0.0121 167. 0.0131 2329500500067 111. 0.0125 168. 0.0136 2329500500068 112. 0.0128 169. 0.0139 2329500500069 113. 0.0133 170. 0.0143 2329500500070 114. 0.0137 171. 0.0147 2329500500071 115. 0.0142 172. 0.0151 2329500500072 116. 0.0146 173. 0.0155 2329500500073 117. 0.0149 174. 0.0159 2329500500074 118. 0.0154 175. 0.0163 2329500500075 119. 0.0159 176. 0.0167 2329500500076 120. 0.0162 177. 0.0171 2329500500077 121. 0.0167 178. 0.0175 2329500500078 122. 0.0171 179. 0.0180 2329500500079 123. 0.0176 180. 0.0183 2329500500080 124. 0.0181 181. 0.0188 2329500500081 125. 0.0182 182. 0.0191 2329500500082 126. 0.0179 183. 0.0190 2329500500083 127. 0.0177 184. 0.0187 2329500500084 128. 0.0175 185. 0.0184 2329500500085 129. 0.0173 186. 0.0182 2329500500086 130. 0.0170 187. 0.0178 2329500500087 131. 0.0167 188. 0.0175 2329500500088 132. 0.0165 189. 0.0171 2329500500089 133. 0.0162 190. 0.0169 2329500500090 134. 0.0160 191. 0.0165 2329500500091 135. 0.0157 192. 0.0162 2329500500092 136. 0.0155 193. 0.0158 2329500500093 137. 0.0152 194. 0.0155 2329500500094 138. 0.0150 195. 0.0151 2329500500095 139. 0.0147 196. 0.0148 2329500500096 140. 0.0144 197. 0.0145 2329500500097 141. 0.0142 198. 0.0141 2329500500098 142. 0.0138 199. 0.0137 2329500500099 143. 0.0136 200. 0.0133 2329500500100 144. 0.0133 201. 0.0130 2329500500101 145. 0.0130 202. 0.0126 2329500500102 146. 0.0128 203. 0.0121 2329500500103 147. 0.0125 204. 0.0118 2329500500104 148. 0.0123 205. 0.0114 2329500500105 149. 0.0120 206. 0.0110 2329500500106 150. 0.0115 207. 0.0106 2329500500107 151. 0.0112 208. 0.0102 2329500500108 152. 0.0109 209. 0.0098 2329500500109 153. 0.0107 210. 0.0093 2329500500110 154. 0.0103 211. 0.0090 2329500500111 155. 0.0100 212. 0.0086 2329500500112 156. 0.0097 213. 0.0081 2329500500113 157. 0.0094 214. 0.0077 2329500500114 158. 0.0089 215. 0.0073 2329500500115 159. 0.0085 216. 0.0068 2329500500116 160. 0.0082 217. 0.0064 2329500500117 161. 0.0078 218. 0.0059 2329500500118 162. 0.0074 219. 0.0055 2329500500119 163. 0.0069 220. 0.0051 2329500500120 164. 0.0065 221. 0.0045 2329500500121 165. 0.0060 222. 0.0041 2329500500122 166. 0.0057 223. 0.0037 2329500500123 167. 0.0053 224. 0.0032 2329500500124 168. 0.0048 225. 0.0027 2329500500125 169. 0.0044 226. 0.0022 2329500500126 170. 0.0040 227. 0.0017 2329500500127 171. 0.0035 228. 0.0012 2329500500128 172. 0.0031 229. 0.0007 2329500500129 173. 0.0026 230. 0.0001 2329500500130 174. 0.0021 2329500500131 175. 0.0017 2329500500132 176. 0.0012 2329500500133 177. 0.0007 2329500500134 178. 0.0002 2329500500135 FACILITY (VDG,2GERKFK) 3.7 MV Van de Graaff 2329500500136 SAMPLE 13C-enriched graphite powder enclosed in Al containers 2329500500137 of 6 mm diameter. Gold foils served as monitors for the2329500500138 neutron fluence; were attached to the 13C sample to 2329500500139 form a stack of 197Au -13C- 197Au. 2329500500140 Additional Measurement: 2329500500141 13C-enriched graphite (98% 13C) from AMT Ltd., Israel ;2329500500142 spurious contents of 14N in the sample material; 2329500500143 irradiated at thermal flux 4*10**1 /sec/cm2 at TRIGA 2329500500144 reactor (epithermal to thermal flux ratio 1.3%) 2329500500145 Irradiation of 2329500500146 Sample C13-1 C13-2 C13-3 2329500500147 Fluence,10**15 /cm2 0.241+-0.010 14.9+-0.7 130+-10 2329500500148 14C/13C, 10**-11at/at 0.25+-0.02 1.60+-0.10 13.5+-1.02329500500149 SIGprod,mb 10.4+-1.0 10.7+-0.9 10.4+-0.92329500500150 Mean value of sample production cross section (contains2329500500151 contribution from N-14(N,P)C-14) is 10.5+-0.6 mb 2329500500152 ( Table I of PR/C,93,045803,2016). 2329500500153 From the measured effective thermal cross section, 2329500500154 SIGprod (the sum of 14C production from 13C(n,gamma) 2329500500155 and 14N(n,p) ), the intrinsic 14N content in the 2329500500156 graphite samples was then determined using the 2329500500157 thermal cross section values for 13C(n,gamma) 1.37mb 2329500500158 and for 14N(n,p) 1860. mb. 2329500500159 MONITOR (79-AU-197(N,G)79-AU-198,,SIG,,SPA) 2329500500160 Spectrum average value. 2329500500161 Used as monitor to determine the neutron fluence. 2329500500162 DECAY-MON (79-AU-198,,DG,411.8) 2329500500163 DETECTOR (HPGE) HPGe well-calibrated to measure the induced Au 2329500500164 activity. 2329500500165 CORRECTION For self-absorption in Au sample. 2329500500166 For decay during irradiation of Au sample. 2329500500167 For amount of C-14 from the N-14 contamination of the 2329500500168 C-13-enriched samples. 2329500500169 ANALYSIS Exp. cross-section SIG was defined as : 2329500500170 SIG=SIGprod - SIG14N*(N14N/N13C), where 2329500500171 SIGprod - sample production cross section, directly 2329500500172 measured to be at 128.keV - 140.+-11.microbarn, 2329500500173 at 182.keV - 103.+-10.microbarn; 2329500500174 SIG14N - N-14(n,p) cross section, 2329500500175 N14N/N13C - isotope ratio : 2329500500176 - defined to be equal 0.0049+-0.0004 as 2329500500177 (SIGprod/SIG13C-1)*(SIG13C/SIG14N) using measured 2329500500178 SIGprod thermal cross section 10.5mb and thermal 2329500500179 cross section C-13(n,g) 1.37+-0.04mb from REL-REF of 2329500500180 Mughabghab, 2329500500181 - in agreement with value 0.005+-0.001 obtained as 2329500500182 direct AMS result. 2329500500183 Measured isotope ratio 14C/13C 2329500500184 for blank - (10+-2)*10**-15, 2329500500185 for En=128 keV - (93+-7)*10**-15 2329500500186 for En=182 keV - (48+-5)*10**-15 2329500500187 ERR-ANALYS (ERR-T) Total uncertainty 8% for 128keV, 12% for 182keV2329500500188 - Neutron fluence uncertainty - 3%, 2329500500189 consist of 2329500500190 (ERR-1) Au cross section 2.0% 2329500500191 (ERR-2) Counting efficiency 2.0% 2329500500192 (ERR-3,,0.5) Gamma intensity per decay <0.5% 2329500500193 (ERR-4,,0.5) Time factors <0.5 2329500500194 - AMS measurement 2329500500195 (ERR-5) Flux anisotropy 3.0% 2329500500196 (ERR-6) 14N-induced background 0.3-0.5 % 2329500500197 (ERR-7) 14C in sample material 7-10 % 2329500500198 (ERR-8) 14C in blank samples 2-4 2329500500199 STATUS (TABLE) Table V of PR/C,93,045803,2016 - data, 2329500500200 Table VI - uncertainties. 2329500500201 ENDBIB 199 0 2329500500202 COMMON 4 3 2329500500203 EN-RSL-HW ERR-1 ERR-2 ERR-5 2329500500204 KEV PER-CENT PER-CENT PER-CENT 2329500500205 30. 2.0 2.0 3.0 2329500500206 ENDCOMMON 3 0 2329500500207 DATA 8 2 2329500500208 EN-MEAN DATA ERR-T MONIT MONIT-ERR ERR-6 2329500500209 ERR-7 ERR-8 2329500500210 KEV MICRO-B MICRO-B MB MB PER-CENT 2329500500211 PER-CENT PER-CENT 2329500500212 128. 136. 11. 293. 6. 0.3 2329500500213 7. 2. 2329500500214 182. 99. 12. 263. 5. 0.5 2329500500215 10. 4. 2329500500216 ENDDATA 8 0 2329500500217 ENDSUBENT 216 0 2329500599999 SUBENT 23295006 20160421 22492329500600001 BIB 5 8 2329500600002 REACTION (6-C-13(N,G)6-C-14,,SIG,,MXW,DERIV) MACS 2329500600003 ANALYSIS MACS were calculated using best-fit cross section to 2329500600004 the measured data. 2329500600005 ADD-RES (COMP) Compared with KADONIS and JEFF-3.2 calculations.2329500600006 ERR-ANALYS (DATA-ERR) Total uncertainty 2329500600007 STATUS (TABLE) Table VII of PR/C,93,045803,2016 2329500600008 (DEP,23295004) 2329500600009 (DEP,23295005) 2329500600010 ENDBIB 8 0 2329500600011 NOCOMMON 0 0 2329500600012 DATA 3 13 2329500600013 KT DATA DATA-ERR 2329500600014 KEV MICRO-B MICRO-B 2329500600015 5. 8.3 1.1 2329500600016 8. 8.1 1.0 2329500600017 10. 8.2 1.4 2329500600018 15. 9.6 1.7 2329500600019 20. 13.8 2.3 2329500600020 23. 17.6 2.5 2329500600021 25. 20.6 2.7 2329500600022 30. 28.7 3.0 2329500600023 40. 43.7 4.9 2329500600024 50. 54.0 6.1 2329500600025 60. 60.1 6.9 2329500600026 80. 65.0 7.9 2329500600027 100. 65.7 8.4 2329500600028 ENDDATA 15 0 2329500600029 ENDSUBENT 28 0 2329500699999 SUBENT 23295007 20160421 22492329500700001 BIB 5 8 2329500700002 REACTION (7-N-14(N,P)6-C-14,,SIG,,MXW,DERIV) MACS 2329500700003 ANALYSIS MACS were calculated using best-fit cross section to 2329500700004 the measured data. 2329500700005 ADD-RES (COMP) Compared with JEFF-3.2 calculations. 2329500700006 ERR-ANALYS (DATA-ERR) Total uncertainty 2329500700007 STATUS (TABLE) Table VII of PR/C,93,045803,2016 2329500700008 (DEP,23295002) 2329500700009 (DEP,23295003) 2329500700010 ENDBIB 8 0 2329500700011 NOCOMMON 0 0 2329500700012 DATA 3 13 2329500700013 KT DATA DATA-ERR 2329500700014 KEV MB MB 2329500700015 5. 3.78 0.06 2329500700016 8. 3.12 0.05 2329500700017 10. 2.89 0.05 2329500700018 15. 2.47 0.04 2329500700019 20. 2.21 0.04 2329500700020 23. 2.09 0.04 2329500700021 25. 2.03 0.04 2329500700022 30. 1.93 0.04 2329500700023 40. 1.85 0.05 2329500700024 50. 1.83 0.06 2329500700025 60. 1.84 0.07 2329500700026 80. 1.84 0.08 2329500700027 100. 1.83 0.08 2329500700028 ENDDATA 15 0 2329500700029 ENDSUBENT 28 0 2329500799999 ENDENTRY 7 0 2329599999999