ENTRY 21599 20160725 22522159900000001 SUBENT 21599001 20160725 22522159900100001 BIB 16 59 2159900100002 INSTITUTE (2AUSIRK) 2159900100003 REFERENCE ((S,INDC(USA)-84,(1),343,1980)= 2159900100004 (S,BNL-NCS-51245,(1),343,1980)) 2159900100005 Full paper of contribution to Symposium on Neutron 2159900100006 Cross Sections from 10-50 MeV, held at Upton, 2159900100007 L.I.(U.S.A.), May, 12-14,1980 2159900100008 (S,ZFK-382,159,197901) no data given. 2159900100009 AUTHOR (H.Vonach,A.Chalupka,F.Wenninger,G.Staffel) 2159900100010 TITLE Measurement of the angle-integrated secondary neutron 2159900100011 spectra from interaction of 14 MeV neutrons with 2159900100012 medium and heavy nuclei 2159900100013 FACILITY (CCW,2AUSIRK) A pulsed 250 keV Cockcroft Walton 2159900100014 accelerator. 2159900100015 INC-SOURCE (D-T) Using a small low-mass titanium-tritium target. 2159900100016 SAMPLE Hollow cylinders of about 6 cm3 with natural isotopic 2159900100017 abundance. 2159900100018 METHOD (TOF) Time of flight techniques. 2159900100019 (PSD) Pulse-shape discrimination on neutron 2159900100020 detector. 2159900100021 DETECTOR (SCIN) An efficiency calibrated NE213 liquid 2159900100022 scintillator. 2159900100023 ANALYSIS (INTAD) Integration of angular distribution. 2159900100024 MONITOR (98-CF-252(0,F),,NU) For detector efficiency 2159900100025 calibration between 0.25 and 6 MeV neutron energy. 2159900100026 (13-AL-27(N,A)11-NA-24,,SIG) For detector efficiency 2159900100027 calibration at 14.7 MeV neutron energy. 2159900100028 COMMENT The experimental results are compared with existing 2159900100029 measurements and with statistical model calculations 2159900100030 using the code STAPRE. 2159900100031 CORRECTION For- 2159900100032 -neutron absorption in the sample, 2159900100033 -multiple scattering, 2159900100034 -relative contribution of neutrons elastically 2159900100035 scattered in sample to 14.7 MeV peak. 2159900100036 ERR-ANALYS (ERR-T) The errors given were obtained by quadratic 2159900100037 addition of the statistical errors estimated 1 sigma 2159900100038 errors for all identified sources of systematic errors2159900100039 and thus correspond to effective 1 sigma errors. The 2159900100040 following contributions are included in the error 2159900100041 estimates, 2159900100042 - the total statistical error including the error 2159900100043 of the Cf-252 calibration measurement, 2159900100044 - the uncertainty in the form of the Cf-252 2159900100045 spectrum, 2159900100046 - the error in the absorption correction factor for 2159900100047 the secondary neutrons, 2159900100048 (ERR-1) the error for the multiple scattering correctio2159900100049 - an uncertainty of 1.5% was assumed for the 2159900100050 normalization factors used in the background 2159900100051 subtraction, 2159900100052 (ERR-2) a 3% efficiency error for the 14.7 MeV 2159900100053 source neutrons. 2159900100054 STATUS (TABLE) Table 1 from 80BNL,1,343,1980 2159900100055 HISTORY (19800610C) CN. 2159900100056 (19800718E) 2159900100057 (20160725A) SD:Updated to new date formats,lower case. 2159900100058 Refs W,VONACH,1980 -> INDC(USA)-84,(1),343; 2159900100059 ZFK-382,,159 -> ZFK-382,159. DATA-ERR -> ERR-T. 2159900100060 ERR-ANALYS update. 2159900100061 ENDBIB 59 0 2159900100062 COMMON 7 6 2159900100063 EN-MEAN MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR ERR-1 2159900100064 ERR-2 2159900100065 MEV NO-DIM NO-DIM MB PER-CENT PER-CENT 2159900100066 PER-CENT 2159900100067 14.1 3.736 0.01 120.4 1.2 1.5 2159900100068 3. 2159900100069 ENDCOMMON 6 0 2159900100070 ENDSUBENT 69 0 2159900199999 SUBENT 21599002 20160725 22522159900200001 BIB 1 2 2159900200002 REACTION (22-TI-0(N,X)0-NN-1,EM,DE) Angle integrated 2159900200003 secondary neutron-production cross section. 2159900200004 ENDBIB 2 0 2159900200005 NOCOMMON 0 0 2159900200006 DATA 4 19 2159900200007 E-MIN E-MAX DATA ERR-T 2159900200008 MEV MEV MB/MEV MB/MEV 2159900200009 0.25 0.50 399. 28. 2159900200010 0.50 0.75 465. 22. 2159900200011 0.75 1.00 499. 23. 2159900200012 1.00 1.25 454. 21. 2159900200013 1.25 1.50 410. 19. 2159900200014 1.50 1.75 359. 16. 2159900200015 1.75 2.00 321. 14. 2159900200016 2.00 2.25 292. 13. 2159900200017 2.25 2.50 253. 12. 2159900200018 2.50 2.75 222. 11. 2159900200019 2.75 3.00 202. 11. 2159900200020 3.00 3.25 171. 9. 2159900200021 3.25 3.50 148. 8. 2159900200022 3.50 3.75 149. 8. 2159900200023 3.75 4.00 129. 8. 2159900200024 4.00 4.50 117. 7. 2159900200025 4.50 5.00 91. 6. 2159900200026 5.00 5.50 73. 5. 2159900200027 5.50 6.00 60. 5. 2159900200028 ENDDATA 21 0 2159900200029 ENDSUBENT 28 0 2159900299999 SUBENT 21599003 20160725 22522159900300001 BIB 1 2 2159900300002 REACTION (24-CR-0(N,X)0-NN-1,EM,DE) Angle integrated 2159900300003 secondary neutron-production cross-section. 2159900300004 ENDBIB 2 0 2159900300005 NOCOMMON 0 0 2159900300006 DATA 4 19 2159900300007 E-MIN E-MAX DATA ERR-T 2159900300008 MEV MEV MB/MEV MB/MEV 2159900300009 0.25 0.50 415. 21. 2159900300010 0.50 0.75 491. 22. 2159900300011 0.75 1.00 473. 22. 2159900300012 1.00 1.25 433. 20. 2159900300013 1.25 1.50 379. 18. 2159900300014 1.50 1.75 340. 15. 2159900300015 1.75 2.00 303. 14. 2159900300016 2.00 2.25 285. 13. 2159900300017 2.25 2.50 243. 12. 2159900300018 2.50 2.75 225. 12. 2159900300019 2.75 3.00 191. 10. 2159900300020 3.00 3.25 169. 9. 2159900300021 3.25 3.50 159. 9. 2159900300022 3.50 3.75 149. 8. 2159900300023 3.75 4.00 134. 7. 2159900300024 4.00 4.50 109. 6. 2159900300025 4.50 5.00 91. 6. 2159900300026 5.00 5.50 70. 5. 2159900300027 5.50 6.00 55. 5. 2159900300028 ENDDATA 21 0 2159900300029 ENDSUBENT 28 0 2159900399999 SUBENT 21599004 20160725 22522159900400001 BIB 1 2 2159900400002 REACTION (26-FE-0(N,X)0-NN-1,EM,DE) Angle integrated 2159900400003 secondary neutron-production cross-section. 2159900400004 ENDBIB 2 0 2159900400005 NOCOMMON 0 0 2159900400006 DATA 4 19 2159900400007 E-MIN E-MAX DATA ERR-T 2159900400008 MEV MEV MB/MEV MB/MEV 2159900400009 0.25 0.50 420. 20. 2159900400010 0.50 0.75 523. 25. 2159900400011 0.75 1.00 502. 24. 2159900400012 1.00 1.25 466. 23. 2159900400013 1.25 1.50 394. 19. 2159900400014 1.50 1.75 349. 17. 2159900400015 1.75 2.00 305. 15. 2159900400016 2.00 2.25 281. 14. 2159900400017 2.25 2.50 237. 12. 2159900400018 2.50 2.75 228. 12. 2159900400019 2.75 3.00 190. 10. 2159900400020 3.00 3.25 175. 9. 2159900400021 3.25 3.50 158. 9. 2159900400022 3.50 3.75 150. 8. 2159900400023 3.75 4.00 130. 7. 2159900400024 4.00 4.50 113. 6. 2159900400025 4.50 5.00 102. 6. 2159900400026 5.00 5.50 82. 5. 2159900400027 5.50 6.00 66. 5. 2159900400028 ENDDATA 21 0 2159900400029 ENDSUBENT 28 0 2159900499999 SUBENT 21599005 20160725 22522159900500001 BIB 1 2 2159900500002 REACTION (28-NI-0(N,X)0-NN-1,EM,DE) Angle integrated 2159900500003 secondary neutron-production cross-section. 2159900500004 ENDBIB 2 0 2159900500005 NOCOMMON 0 0 2159900500006 DATA 4 19 2159900500007 E-MIN E-MAX DATA ERR-T 2159900500008 MEV MEV MB/MEV MB/MEV 2159900500009 0.25 0.50 319. 16. 2159900500010 0.50 0.75 378. 16. 2159900500011 0.75 1.00 381. 16. 2159900500012 1.00 1.25 346. 15. 2159900500013 1.25 1.50 297. 13. 2159900500014 1.50 1.75 257. 11. 2159900500015 1.75 2.00 224. 9. 2159900500016 2.00 2.25 202. 9. 2159900500017 2.25 2.50 168. 8. 2159900500018 2.50 2.75 169. 8. 2159900500019 2.75 3.00 140. 7. 2159900500020 3.00 3.25 120. 6. 2159900500021 3.25 3.50 119. 6. 2159900500022 3.50 3.75 110. 6. 2159900500023 3.75 4.00 100. 5. 2159900500024 4.00 4.50 89. 4. 2159900500025 4.50 5.00 80. 4. 2159900500026 5.00 5.50 63. 4. 2159900500027 5.50 6.00 52. 3. 2159900500028 ENDDATA 21 0 2159900500029 ENDSUBENT 28 0 2159900599999 SUBENT 21599006 20160725 22522159900600001 BIB 1 2 2159900600002 REACTION (29-CU-0(N,X)0-NN-1,EM,DE) Angle integrated 2159900600003 secondary neutron-production cross-section. 2159900600004 ENDBIB 2 0 2159900600005 NOCOMMON 0 0 2159900600006 DATA 4 19 2159900600007 E-MIN E-MAX DATA ERR-T 2159900600008 MEV MEV MB/MEV MB/MEV 2159900600009 0.25 0.50 604. 26. 2159900600010 0.50 0.75 730. 34. 2159900600011 0.75 1.00 699. 34. 2159900600012 1.00 1.25 619. 30. 2159900600013 1.25 1.50 531. 26. 2159900600014 1.50 1.75 445. 21. 2159900600015 1.75 2.00 378. 19. 2159900600016 2.00 2.25 335. 17. 2159900600017 2.25 2.50 285. 15. 2159900600018 2.50 2.75 256. 14. 2159900600019 2.75 3.00 221. 14. 2159900600020 3.00 3.25 180. 11. 2159900600021 3.25 3.50 163. 10. 2159900600022 3.50 3.75 151. 10. 2159900600023 3.75 4.00 140. 9. 2159900600024 4.00 4.50 110. 7. 2159900600025 4.50 5.00 95. 7. 2159900600026 5.00 5.50 73. 6. 2159900600027 5.50 6.00 53. 6. 2159900600028 ENDDATA 21 0 2159900600029 ENDSUBENT 28 0 2159900699999 SUBENT 21599007 20160725 22522159900700001 BIB 1 2 2159900700002 REACTION (30-ZN-0(N,X)0-NN-1,EM,DE) Angle integrated 2159900700003 secondary neutron-production cross section. 2159900700004 ENDBIB 2 0 2159900700005 NOCOMMON 0 0 2159900700006 DATA 4 19 2159900700007 E-MIN E-MAX DATA ERR-T 2159900700008 MEV MEV MB/MEV MB/MEV 2159900700009 0.25 0.50 422. 10. 2159900700010 0.50 0.75 519. 23. 2159900700011 0.75 1.00 510. 23. 2159900700012 1.00 1.25 448. 20. 2159900700013 1.25 1.50 376. 17. 2159900700014 1.50 1.75 324. 14. 2159900700015 1.75 2.00 286. 13. 2159900700016 2.00 2.25 254. 12. 2159900700017 2.25 2.50 224. 11. 2159900700018 2.50 2.75 199. 10. 2159900700019 2.75 3.00 175. 9. 2159900700020 3.00 3.25 146. 8. 2159900700021 3.25 3.50 131. 7. 2159900700022 3.50 3.75 122. 7. 2159900700023 3.75 4.00 105. 7. 2159900700024 4.00 4.50 85. 5. 2159900700025 4.50 5.00 74. 5. 2159900700026 5.00 5.50 60. 4. 2159900700027 5.50 6.00 46. 4. 2159900700028 ENDDATA 21 0 2159900700029 ENDSUBENT 28 0 2159900799999 SUBENT 21599008 20160725 22522159900800001 BIB 1 2 2159900800002 REACTION (40-ZR-0(N,X)0-NN-1,EM,DE) Angle integrated 2159900800003 secondary neutron-production cross-section. 2159900800004 ENDBIB 2 0 2159900800005 NOCOMMON 0 0 2159900800006 DATA 4 19 2159900800007 E-MIN E-MAX DATA ERR-T 2159900800008 MEV MEV MB/MEV MB/MEV 2159900800009 0.25 0.50 1208. 36. 2159900800010 0.50 0.75 1256. 53. 2159900800011 0.75 1.00 1136. 49. 2159900800012 1.00 1.25 960. 42. 2159900800013 1.25 1.50 815. 36. 2159900800014 1.50 1.75 681. 29. 2159900800015 1.75 2.00 538. 24. 2159900800016 2.00 2.25 462. 21. 2159900800017 2.25 2.50 362. 19. 2159900800018 2.50 2.75 291. 17. 2159900800019 2.75 3.00 230. 15. 2159900800020 3.00 3.25 173. 13. 2159900800021 3.25 3.50 150. 12. 2159900800022 3.50 3.75 139. 12. 2159900800023 3.75 4.00 114. 11. 2159900800024 4.00 4.50 84. 9. 2159900800025 4.50 5.00 61. 9. 2159900800026 5.00 5.50 31. 9. 2159900800027 5.50 6.00 31. 9. 2159900800028 ENDDATA 21 0 2159900800029 ENDSUBENT 28 0 2159900899999 SUBENT 21599009 20160725 22522159900900001 BIB 1 2 2159900900002 REACTION (41-NB-93(N,X)0-NN-1,EM,DE) Angle integrated 2159900900003 secondary neutron-production cross-section. 2159900900004 ENDBIB 2 0 2159900900005 NOCOMMON 0 0 2159900900006 DATA 4 19 2159900900007 E-MIN E-MAX DATA ERR-T 2159900900008 MEV MEV MB/MEV MB/MEV 2159900900009 0.25 0.50 1256. 66. 2159900900010 0.50 0.75 1360. 60. 2159900900011 0.75 1.00 1252. 57. 2159900900012 1.00 1.25 1043. 49. 2159900900013 1.25 1.50 895. 42. 2159900900014 1.50 1.75 782. 36. 2159900900015 1.75 2.00 655. 31. 2159900900016 2.00 2.25 568. 27. 2159900900017 2.25 2.50 459. 24. 2159900900018 2.50 2.75 380. 21. 2159900900019 2.75 3.00 317. 18. 2159900900020 3.00 3.25 257. 15. 2159900900021 3.25 3.50 212. 14. 2159900900022 3.50 3.75 196. 13. 2159900900023 3.75 4.00 161. 12. 2159900900024 4.00 4.50 109. 8. 2159900900025 4.50 5.00 87. 8. 2159900900026 5.00 5.50 65. 8. 2159900900027 5.50 6.00 68. 8. 2159900900028 ENDDATA 21 0 2159900900029 ENDSUBENT 28 0 2159900999999 SUBENT 21599010 20160725 22522159901000001 BIB 1 2 2159901000002 REACTION (42-MO-0(N,X)0-NN-1,EM,DE) Angle integrated 2159901000003 secondary neutron-production cross-section. 2159901000004 ENDBIB 2 0 2159901000005 NOCOMMON 0 0 2159901000006 DATA 4 19 2159901000007 E-MIN E-MAX DATA ERR-T 2159901000008 MEV MEV MB/MEV MB/MEV 2159901000009 0.25 0.50 1185. 39. 2159901000010 0.50 0.75 1418. 64. 2159901000011 0.75 1.00 1243. 58. 2159901000012 1.00 1.25 1030. 49. 2159901000013 1.25 1.50 848. 41. 2159901000014 1.50 1.75 710. 33. 2159901000015 1.75 2.00 585. 28. 2159901000016 2.00 2.25 506. 24. 2159901000017 2.25 2.50 415. 22. 2159901000018 2.50 2.75 361. 19. 2159901000019 2.75 3.00 293. 16. 2159901000020 3.00 3.25 237. 13. 2159901000021 3.25 3.50 202. 12. 2159901000022 3.50 3.75 168. 11. 2159901000023 3.75 4.00 141. 10. 2159901000024 4.00 4.50 115. 7. 2159901000025 4.50 5.00 87. 7. 2159901000026 5.00 5.50 70. 6. 2159901000027 5.50 6.00 50. 6. 2159901000028 ENDDATA 21 0 2159901000029 ENDSUBENT 28 0 2159901099999 SUBENT 21599011 20160725 22522159901100001 BIB 1 2 2159901100002 REACTION (47-AG-0(N,X)0-NN-1,EM,DE) Angle integrated 2159901100003 secondary neutron-production cross-section. 2159901100004 ENDBIB 2 0 2159901100005 NOCOMMON 0 0 2159901100006 DATA 4 19 2159901100007 E-MIN E-MAX DATA ERR-T 2159901100008 MEV MEV MB/MEV MB/MEV 2159901100009 0.25 0.50 1669. 96. 2159901100010 0.50 0.75 1689. 83. 2159901100011 0.75 1.00 1450. 74. 2159901100012 1.00 1.25 1146. 60. 2159901100013 1.25 1.50 923. 49. 2159901100014 1.50 1.75 786. 41. 2159901100015 1.75 2.00 617. 33. 2159901100016 2.00 2.25 545. 30. 2159901100017 2.25 2.50 406. 24. 2159901100018 2.50 2.75 380. 22. 2159901100019 2.75 3.00 289. 20. 2159901100020 3.00 3.25 224. 15. 2159901100021 3.25 3.50 199. 14. 2159901100022 3.50 3.75 177. 13. 2159901100023 3.75 4.00 145. 12. 2159901100024 4.00 4.50 108. 9. 2159901100025 4.50 5.00 91. 9. 2159901100026 5.00 5.50 73. 9. 2159901100027 5.50 6.00 66. 9. 2159901100028 ENDDATA 21 0 2159901100029 ENDSUBENT 28 0 2159901199999 SUBENT 21599012 20160725 22522159901200001 BIB 1 2 2159901200002 REACTION (50-SN-0(N,X)0-NN-1,EM,DE) Angle integrated 2159901200003 secondary neutron-production cross-section. 2159901200004 ENDBIB 2 0 2159901200005 NOCOMMON 0 0 2159901200006 DATA 4 19 2159901200007 E-MIN E-MAX DATA ERR-T 2159901200008 MEV MEV MB/MEV MB/MEV 2159901200009 0.25 0.50 1495. 44. 2159901200010 0.50 0.75 1675. 69. 2159901200011 0.75 1.00 1566. 67. 2159901200012 1.00 1.25 1305. 56. 2159901200013 1.25 1.50 1062. 46. 2159901200014 1.50 1.75 878. 37. 2159901200015 1.75 2.00 700. 30. 2159901200016 2.00 2.25 608. 27. 2159901200017 2.25 2.50 463. 22. 2159901200018 2.50 2.75 362. 19. 2159901200019 2.75 3.00 300. 17. 2159901200020 3.00 3.25 233. 14. 2159901200021 3.25 3.50 180. 13. 2159901200022 3.50 3.75 177. 13. 2159901200023 3.75 4.00 145. 12. 2159901200024 4.00 4.50 109. 9. 2159901200025 4.50 5.00 88. 9. 2159901200026 5.00 5.50 66. 9. 2159901200027 5.50 6.00 30. 8. 2159901200028 ENDDATA 21 0 2159901200029 ENDSUBENT 28 0 2159901299999 SUBENT 21599013 20160725 22522159901300001 BIB 1 2 2159901300002 REACTION (56-BA-0(N,X)0-NN-1,EM,DE) Angle integrated 2159901300003 secondary neutron-production cross-section. 2159901300004 ENDBIB 2 0 2159901300005 NOCOMMON 0 0 2159901300006 DATA 4 19 2159901300007 E-MIN E-MAX DATA ERR-T 2159901300008 MEV MEV MB/MEV MB/MEV 2159901300009 0.25 0.50 1500. 62. 2159901300010 0.50 0.75 1443. 72. 2159901300011 0.75 1.00 1465. 70. 2159901300012 1.00 1.25 1292. 62. 2159901300013 1.25 1.50 1051. 52. 2159901300014 1.50 1.75 834. 43. 2159901300015 1.75 2.00 688. 38. 2159901300016 2.00 2.25 561. 35. 2159901300017 2.25 2.50 420. 32. 2159901300018 2.50 2.75 365. 33. 2159901300019 2.75 3.00 287. 33. 2159901300020 3.00 3.25 262. 28. 2159901300021 3.25 3.50 215. 28. 2159901300022 3.50 3.75 174. 28. 2159901300023 3.75 4.00 202. 28. 2159901300024 4.00 4.50 165. 21. 2159901300025 4.50 5.00 97. 22. 2159901300026 5.00 5.50 57. 20. 2159901300027 5.50 6.00 26. 12. 2159901300028 ENDDATA 21 0 2159901300029 ENDSUBENT 28 0 2159901399999 SUBENT 21599014 20160725 22522159901400001 BIB 1 2 2159901400002 REACTION (73-TA-0(N,X)0-NN-1,EM,DE) Angle integrated 2159901400003 secondary neutron-production cross-section. 2159901400004 ENDBIB 2 0 2159901400005 NOCOMMON 0 0 2159901400006 DATA 4 19 2159901400007 E-MIN E-MAX DATA ERR-T 2159901400008 MEV MEV MB/MEV MB/MEV 2159901400009 0.25 0.50 2151. 118. 2159901400010 0.50 0.75 2458. 123. 2159901400011 0.75 1.00 2186. 113. 2159901400012 1.00 1.25 1750. 92. 2159901400013 1.25 1.50 1360. 72. 2159901400014 1.50 1.75 1069. 56. 2159901400015 1.75 2.00 833. 45. 2159901400016 2.00 2.25 671. 37. 2159901400017 2.25 2.50 505. 30. 2159901400018 2.50 2.75 403. 23. 2159901400019 2.75 3.00 278. 18. 2159901400020 3.00 3.25 230. 15. 2159901400021 3.25 3.50 193. 13. 2159901400022 3.50 3.75 154. 12. 2159901400023 3.75 4.00 142. 11. 2159901400024 4.00 4.50 93. 8. 2159901400025 4.50 5.00 82. 2. 2159901400026 5.00 5.50 59. 8. 2159901400027 5.50 6.00 55. 8. 2159901400028 ENDDATA 21 0 2159901400029 ENDSUBENT 28 0 2159901499999 SUBENT 21599015 20160725 22522159901500001 BIB 1 2 2159901500002 REACTION (74-W-0(N,X)0-NN-1,EM,DE) Angle integrated 2159901500003 secondary neutron-production cross-section. 2159901500004 ENDBIB 2 0 2159901500005 NOCOMMON 0 0 2159901500006 DATA 4 19 2159901500007 E-MIN E-MAX DATA ERR-T 2159901500008 MEV MEV MB/MEV MB/MEV 2159901500009 0.25 0.50 2123. 70. 2159901500010 0.50 0.75 2508. 115. 2159901500011 0.75 1.00 2347. 111. 2159901500012 1.00 1.25 1844. 89. 2159901500013 1.25 1.50 1469. 72. 2159901500014 1.50 1.75 1139. 55. 2159901500015 1.75 2.00 887. 44. 2159901500016 2.00 2.25 704. 36. 2159901500017 2.25 2.50 527. 30. 2159901500018 2.50 2.75 425. 26. 2159901500019 2.75 3.00 289. 25. 2159901500020 3.00 3.25 243. 19. 2159901500021 3.25 3.50 207. 17. 2159901500022 3.50 3.75 161. 17. 2159901500023 3.75 4.00 126. 15. 2159901500024 4.00 4.50 102. 12. 2159901500025 4.50 5.00 53. 12. 2159901500026 5.00 5.50 50. 13. 2159901500027 5.50 6.00 54. 12. 2159901500028 ENDDATA 21 0 2159901500029 ENDSUBENT 28 0 2159901599999 SUBENT 21599016 20160725 22522159901600001 BIB 1 2 2159901600002 REACTION (79-AU-197(N,X)0-NN-1,EM,DE) Angle integrated 2159901600003 secondary neutron-production cross section. 2159901600004 ENDBIB 2 0 2159901600005 NOCOMMON 0 0 2159901600006 DATA 4 19 2159901600007 E-MIN E-MAX DATA ERR-T 2159901600008 MEV MEV MB/MEV MB/MEV 2159901600009 0.25 0.50 1958. 72. 2159901600010 0.50 0.75 2364. 118. 2159901600011 0.75 1.00 2243. 116. 2159901600012 1.00 1.25 1922. 101. 2159901600013 1.25 1.50 1586. 84. 2159901600014 1.50 1.75 1346. 70. 2159901600015 1.75 2.00 1120. 59. 2159901600016 2.00 2.25 870. 47. 2159901600017 2.25 2.50 685. 39. 2159901600018 2.50 2.75 619. 33. 2159901600019 2.75 3.00 484. 28. 2159901600020 3.00 3.25 369. 22. 2159901600021 3.25 3.50 289. 18. 2159901600022 3.50 3.75 249. 17. 2159901600023 3.75 4.00 213. 15. 2159901600024 4.00 4.50 147. 11. 2159901600025 4.50 5.00 114. 11. 2159901600026 5.00 5.50 82. 10. 2159901600027 5.50 6.00 40. 10. 2159901600028 ENDDATA 21 0 2159901600029 ENDSUBENT 28 0 2159901699999 SUBENT 21599017 20160725 22522159901700001 BIB 1 2 2159901700002 REACTION (82-PB-0(N,X)0-NN-1,EM,DE) Angle integrated 2159901700003 secondary neutron-production cross-section. 2159901700004 ENDBIB 2 0 2159901700005 NOCOMMON 0 0 2159901700006 DATA 4 19 2159901700007 E-MIN E-MAX DATA ERR-T 2159901700008 MEV MEV MB/MEV MB/MEV 2159901700009 0.25 0.50 1447. 62. 2159901700010 0.50 0.75 1809. 79. 2159901700011 0.75 1.00 1885. 83. 2159901700012 1.00 1.25 1705. 76. 2159901700013 1.25 1.50 1595. 71. 2159901700014 1.50 1.75 1422. 61. 2159901700015 1.75 2.00 1244. 54. 2159901700016 2.00 2.25 1121. 49. 2159901700017 2.25 2.50 899. 43. 2159901700018 2.50 2.75 741. 38. 2159901700019 2.75 3.00 526. 31. 2159901700020 3.00 3.25 424. 26. 2159901700021 3.25 3.50 380. 24. 2159901700022 3.50 3.75 304. 22. 2159901700023 3.75 4.00 232. 20. 2159901700024 4.00 4.50 183. 15. 2159901700025 4.50 5.00 136. 15. 2159901700026 5.00 5.50 83. 14. 2159901700027 5.50 6.00 65. 15. 2159901700028 ENDDATA 21 0 2159901700029 ENDSUBENT 28 0 2159901799999 SUBENT 21599018 20160725 22522159901800001 BIB 1 2 2159901800002 REACTION (83-BI-209(N,X)0-NN-1,EM,DE) Angle integrated 2159901800003 secondary neutron-production cross-section. 2159901800004 ENDBIB 2 0 2159901800005 NOCOMMON 0 0 2159901800006 DATA 4 19 2159901800007 E-MIN E-MAX DATA ERR-T 2159901800008 MEV MEV MB/MEV MB/MEV 2159901800009 0.25 0.50 1701. 58. 2159901800010 0.50 0.75 1873. 80. 2159901800011 0.75 1.00 1932. 84. 2159901800012 1.00 1.25 1845. 80. 2159901800013 1.25 1.50 1691. 73. 2159901800014 1.50 1.75 1520. 63. 2159901800015 1.75 2.00 1346. 56. 2159901800016 2.00 2.25 1189. 51. 2159901800017 2.25 2.50 999. 46. 2159901800018 2.50 2.75 817. 40. 2159901800019 2.75 3.00 648. 34. 2159901800020 3.00 3.25 514. 28. 2159901800021 3.25 3.50 409. 24. 2159901800022 3.50 3.75 324. 21. 2159901800023 3.75 4.00 277. 20. 2159901800024 4.00 4.50 219. 15. 2159901800025 4.50 5.00 161. 14. 2159901800026 5.00 5.50 97. 13. 2159901800027 5.50 6.00 75. 14. 2159901800028 ENDDATA 21 0 2159901800029 ENDSUBENT 28 0 2159901899999 ENDENTRY 18 0 2159999999999