ENTRY 10421 20030221 00001042100000001 SUBENT 10421001 20030221 00001042100100001 BIB 8 14 1042100100002 INSTITUTE (1USAANL) 1042100100003 REFERENCE (J,NSE,57,300,197508) 1042100100004 (W,POENITZ,197409) 1042100100005 AUTHOR (W.P.Poenitz) 1042100100006 TITLE Measurements of the Neutron Capture Cross Sections of 1042100100007 Gold-197 and Uranium-238 Between 20 and 3500 keV 1042100100008 FACILITY (DYNAM,1USAANL) Tandem dynamitron 1042100100009 INC-SOURCE (P-LI7) 1042100100010 STATUS (APRVD) Approved by author. 1042100100011 Data taken from tables in reference. 1042100100012 HISTORY (19740916C) 1042100100013 (19751120U) BIB changes 1042100100014 (19820602A) Converted to REACTION formalism 1042100100015 (20030221A) Converted to new date formats, lower case. 1042100100016 ENDBIB 14 0 1042100100017 NOCOMMON 0 0 1042100100018 ENDSUBENT 17 0 1042100199999 SUBENT 10421002 20030221 00001042100200001 BIB 7 20 1042100200002 REACTION ((92-U-238(N,G)92-U-239,,SIG)/ 1042100200003 (79-AU-197(N,G)79-AU-198,,SIG)) 1042100200004 METHOD (TOF) Time-of-flight. Flight path - 250 cm. 1042100200005 DETECTOR (STANK) 1300-l liquid scintillator tank for gamma-ray 1042100200006 detection. 1042100200007 6Li glass used as flux monitor. 1042100200008 CORRECTION Corrected for: 1042100200009 . capture of neutrons scattered in samples 1042100200010 . flux attenuation in samples 1042100200011 . transmission thru samples 1042100200012 . gamma-ray detection efficiency 1042100200013 ERR-ANALYS (DATA-ERR) Data errors given include- 1042100200014 . statistics (1-3%), 1042100200015 . sample mass (1%), 1042100200016 . fission gammas (0-5%), 1042100200017 . capture detection efficiency (6-8%), 1042100200018 . capture of scattered neutrons (2%). 1042100200019 FLAG (1.) First set of measurements 1042100200020 (2.) Second set of measurements 1042100200021 HISTORY (19830607A) BIB correction. 1042100200022 ENDBIB 20 0 1042100200023 NOCOMMON 0 0 1042100200024 DATA 5 44 1042100200025 EN EN-RSL DATA DATA-ERR FLAG 1042100200026 KEV KEV NO-DIM NO-DIM NO-DIM 1042100200027 20. 4. 0.876 0.074 1. 1042100200028 24. 0.839 0.070 1. 1042100200029 28. 0.817 0.069 1. 1042100200030 32. 0.832 0.070 1. 1042100200031 36. 0.837 0.070 1. 1042100200032 40. 0.871 0.073 1. 1042100200033 44. 0.839 0.070 1. 1042100200034 48. 0.791 0.066 1. 1042100200035 52. 0.733 0.062 1. 1042100200036 56. 0.740 0.062 1. 1042100200037 60. 0.711 0.060 1. 1042100200038 64. 0.723 0.061 1. 1042100200039 68. 0.641 0.054 1. 1042100200040 72. 0.656 0.055 1. 1042100200041 76. 0.649 0.054 1. 1042100200042 80. 0.635 0.053 1. 1042100200043 85. 10. 0.631 0.053 1. 1042100200044 90. 20. 0.624 0.052 2. 1042100200045 95. 10. 0.593 0.050 1. 1042100200046 105. 10. 0.596 0.050 1. 1042100200047 110. 20. 0.612 0.051 2. 1042100200048 115. 10. 0.588 0.049 1. 1042100200049 125. 10. 0.558 0.047 1. 1042100200050 130. 20. 0.560 0.047 2. 1042100200051 135. 10. 0.538 0.045 1. 1042100200052 145. 10. 0.575 0.048 1. 1042100200053 150. 20. 0.549 0.046 2. 1042100200054 155. 10. 0.562 0.047 1. 1042100200055 170. 20. 0.570 0.047 2. 1042100200056 190. 20. 0.540 0.045 2. 1042100200057 210. 20. 0.571 0.048 2. 1042100200058 230. 20. 0.545 0.046 2. 1042100200059 250. 20. 0.537 0.045 2. 1042100200060 270. 20. 0.557 0.047 2. 1042100200061 290. 20. 0.600 0.051 2. 1042100200062 310. 20. 0.638 0.054 2. 1042100200063 330. 20. 0.625 0.053 2. 1042100200064 350. 20. 0.648 0.054 2. 1042100200065 370. 20. 0.707 0.059 2. 1042100200066 390. 20. 0.673 0.057 2. 1042100200067 410. 20. 0.691 0.058 2. 1042100200068 430. 20. 0.748 0.063 2. 1042100200069 450. 20. 0.793 0.067 2. 1042100200070 470. 20. 0.800 0.067 2. 1042100200071 ENDDATA 46 0 1042100200072 ENDSUBENT 71 0 1042100299999 SUBENT 10421003 20030221 00001042100300001 BIB 8 20 1042100300002 REACTION (92-U-238(N,G)92-U-239,,SIG) 1042100300003 METHOD (TOF) Time-of-flight. Flight PATH - 250 CM. 1042100300004 DETECTOR (STANK) 1300-l liquid scintillator tank for gamma-ray 1042100300005 detection. 1042100300006 6Li glass used as flux monitor. 1042100300007 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) Relative standard 1042100300008 CORRECTION Corrected for: 1042100300009 . capture of neutrons scattered in samples, 1042100300010 . flux attenuation in samples, 1042100300011 . transmission thru samples, 1042100300012 . gamma-ray detection efficiency. 1042100300013 ERR-ANALYS (DATA-ERR) Data errors given include: 1042100300014 . statistics (1-3%), 1042100300015 . sample mass (1%), 1042100300016 . fission gammas (0-5%), 1042100300017 . capture detection efficiency (6-8%), 1042100300018 . capture of scattered neutrons (2%). 1042100300019 . standard error 1042100300020 STATUS (DEP,10421002) Calculated from measured 238U/Au ratios.1042100300021 HISTORY (19830607A) BIB correction. 1042100300022 ENDBIB 20 0 1042100300023 NOCOMMON 0 0 1042100300024 DATA 6 44 1042100300025 EN EN-RSL DATA DATA-ERR MONIT MONIT-ERR 1042100300026 KEV KEV MB MB MB PER-CENT 1042100300027 20. 4. 631. 54. 720. 2. 1042100300028 24. 550. 47. 655. 2. 1042100300029 28. 490. 42. 600. 2. 1042100300030 32. 459. 39. 552. 2. 1042100300031 36. 434. 37. 518. 2. 1042100300032 40. 425. 37. 488. 2. 1042100300033 44. 389. 33. 464. 2. 1042100300034 48. 353. 30. 446. 2. 1042100300035 52. 315. 27. 430. 2. 1042100300036 56. 305. 26. 412. 2. 1042100300037 60. 284. 24. 400. 2. 1042100300038 64. 278. 24. 385. 2. 1042100300039 68. 238. 20. 372. 2. 1042100300040 72. 237. 20. 362. 2. 1042100300041 76. 228. 20. 351. 2. 1042100300042 80. 220. 19. 346. 2. 1042100300043 85. 10. 213. 18. 338. 2. 1042100300044 90. 20. 206. 18. 330. 2. 1042100300045 95. 10. 192. 17. 324. 2. 1042100300046 105. 10. 187. 16. 313. 2. 1042100300047 110. 20. 190. 16. 310. 2. 1042100300048 115. 10. 181. 16. 308. 2. 1042100300049 125. 10. 167. 14. 300. 2. 1042100300050 130. 20. 168. 14. 300. 2. 1042100300051 135. 10. 161. 14. 299. 3. 1042100300052 145. 10. 166. 14. 299. 3. 1042100300053 150. 20. 164. 14. 298. 3. 1042100300054 155. 10. 167. 14. 299. 3. 1042100300055 170. 20. 166. 14. 291. 3. 1042100300056 190. 20. 151. 13. 280. 3. 1042100300057 210. 151. 13. 264. 3. 1042100300058 230. 20. 137. 12. 251. 3. 1042100300059 250. 20. 127. 11. 237. 4. 1042100300060 270. 20. 125. 11. 225. 4. 1042100300061 290. 20. 129. 11. 215. 4. 1042100300062 310. 20. 130. 11. 203. 4. 1042100300063 330. 20. 121. 10. 193. 4. 1042100300064 350. 20. 119. 10. 183. 4. 1042100300065 370. 20. 124. 10. 175. 4. 1042100300066 390. 20. 113. 10. 168. 5. 1042100300067 410. 20. 112. 10. 162. 5. 1042100300068 430. 20. 117. 10. 157. 5. 1042100300069 450. 20. 120. 10. 151. 5. 1042100300070 470. 20. 117. 10. 146. 6. 1042100300071 ENDDATA 46 0 1042100300072 ENDSUBENT 71 0 1042100399999 SUBENT 10421004 20030221 00001042100400001 BIB 5 25 1042100400002 REACTION (79-AU-197(N,G)79-AU-198,,SIG) 1042100400003 DETECTOR (STANK) 1300-l liquid scintillator tank for gamma-ray 1042100400004 detection. 1042100400005 Grey neutron detector used as neutron flux monitor. 1042100400006 Black neutron detector used to obtain absolute neutron 1042100400007 flux at 1000 keV. 1042100400008 CORRECTION Corrected for: 1042100400009 . capture of neutrons scattered in samples, 1042100400010 . flux attenuation in samples, 1042100400011 . transmission thru samples, 1042100400012 . gamma-ray detection efficiency, 1042100400013 . neutron transmission thru air between sample and 1042100400014 detector, 1042100400015 . detection of non-monoenergetic neutrons, 1042100400016 . neutron detector efficiency. 1042100400017 ERR-ANALYS (DATA-ERR) Data errors given include: 1042100400018 . statistics (1-3%), 1042100400019 . sample mass (1%), 1042100400020 . fission gammas (0-5%), 1042100400021 . capture detection efficiency (6-8%), 1042100400022 . capture of scattered neutrons (2%), 1042100400023 . neutron detector efficiency (GND) (1-3%), 1042100400024 (BND) (1-2%), 1042100400025 . scattering in detector (1%). 1042100400026 HISTORY (19820602A) DATA correction. 1042100400027 ENDBIB 25 0 1042100400028 NOCOMMON 0 0 1042100400029 DATA 4 18 1042100400030 EN EN-RSL DATA DATA-ERR 1042100400031 KEV KEV MB MB 1042100400032 400. 27. 177. 16. 1042100400033 500. 26. 145. 13. 1042100400034 600. 25. 117. 11. 1042100400035 700. 24. 100. 10. 1042100400036 850. 23. 85.7 8.0 1042100400037 900. 23. 83.8 7.8 1042100400038 1000. 22. 83.0 6.4 1042100400039 1200. 21. 73.9 7.2 1042100400040 1300. 21. 74.1 6.6 1042100400041 1400. 20. 71.0 6.3 1042100400042 1500. 20. 72.5 6.4 1042100400043 1700. 19. 63.9 6.7 1042100400044 1800. 19. 64.6 6.5 1042100400045 2000. 18. 55.1 6.7 1042100400046 2100. 18. 49.4 5.5 1042100400047 2500. 17. 38.5 4.4 1042100400048 3000. 15. 31.8 3.6 1042100400049 3500. 13. 20.5 2.4 1042100400050 ENDDATA 20 0 1042100400051 ENDSUBENT 50 0 1042100499999 SUBENT 10421005 20030221 00001042100500001 BIB 4 20 1042100500002 REACTION ((92-U-238(N,G)92-U-239,,SIG)/ 1042100500003 (79-AU-197(N,G)79-AU-198,,SIG)) 1042100500004 DETECTOR (STANK) 1300-l liquid scintillator tank for gamma-ray 1042100500005 detection. 1042100500006 Grey neutron detector used as neutron flux monitor. 1042100500007 CORRECTION Corrected for: 1042100500008 . capture of neutrons scattered in samples, 1042100500009 . flux attenuation in samples, 1042100500010 . transmission thru samples, 1042100500011 . gamma-ray detection efficiency, 1042100500012 . neutron transmission thru air between sample and 1042100500013 detector, 1042100500014 . detection of non-monoenergetic neutrons. 1042100500015 ERR-ANALYS (DATA-ERR) Data errors given include: 1042100500016 . statistics (1-3%), 1042100500017 . sample mass (1%), 1042100500018 . fission gammas (0-5%), 1042100500019 . capture detection efficiency (6-8%), 1042100500020 . capture of scattered neutrons (2%), 1042100500021 . standard error. 1042100500022 ENDBIB 20 0 1042100500023 NOCOMMON 0 0 1042100500024 DATA 4 10 1042100500025 EN EN-RSL DATA DATA-ERR 1042100500026 KEV KEV NO-DIM NO-DIM 1042100500027 400. 27. 0.672 0.056 1042100500028 500. 26. 0.858 0.072 1042100500029 600. 25. 1.053 0.088 1042100500030 700. 24. 1.378 0.116 1042100500031 800. 23. 1.450 0.122 1042100500032 850. 23. 1.531 0.130 1042100500033 900. 23. 1.687 0.145 1042100500034 1000. 22. 1.672 0.144 1042100500035 1100. 22. 1.501 0.137 1042100500036 1200. 21. 1.411 0.138 1042100500037 ENDDATA 12 0 1042100500038 ENDSUBENT 37 0 1042100599999 SUBENT 10421006 20030221 00001042100600001 BIB 7 22 1042100600002 REACTION (92-U-238(N,G)92-U-239,,SIG) 1042100600003 DETECTOR (STANK) 1300-l liquid scintillator tank for gamma-ray 1042100600004 detection. 1042100600005 Grey neutron detector used as neutron flux monitor. 1042100600006 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 1042100600007 RELATIVE TO AU(N,GAMMA) 1042100600008 CORRECTION Corrected for: 1042100600009 . capture of neutrons scattered in samples, 1042100600010 . flux attenuation in samples, 1042100600011 . transmission thru samples, 1042100600012 . gamma-ray detection efficiency, 1042100600013 . detection of non-monoenergetic neutrons, 1042100600014 . neutron detector efficiency. 1042100600015 ERR-ANALYS (DATA-ERR) Data errors given include: 1042100600016 . statistics (1-3%), 1042100600017 . sample mass (1%), 1042100600018 . fission gammas (0-5%), 1042100600019 . capture detection efficiency (6-8%), 1042100600020 . capture of scattered neutrons (2%), 1042100600021 . standard error. 1042100600022 STATUS (DEP,10421005) Calculated from measured 238U/Au ratios.1042100600023 HISTORY (19830607A) BIB correction. 1042100600024 ENDBIB 22 0 1042100600025 NOCOMMON 0 0 1042100600026 DATA 6 10 1042100600027 EN EN-RSL DATA DATA-ERR MONIT MONIT-ERR 1042100600028 KEV KEV MB MB MB PER-CENT 1042100600029 400. 27. 111. 10. 165. 6. 1042100600030 500. 26. 118. 10. 138. 6. 1042100600031 600. 25. 124. 10. 118. 6. 1042100600032 700. 24. 138. 12. 100. 7. 1042100600033 800. 23. 130. 11. 90. 7. 1042100600034 850. 23. 132. 11. 86.5 7. 1042100600035 900. 23. 143. 12. 84.5 8. 1042100600036 1000. 22. 135. 12. 80.5 8. 1042100600037 1100. 22. 116. 11. 77.5 8. 1042100600038 1200. 21. 106. 10. 75.0 8. 1042100600039 ENDDATA 12 0 1042100600040 ENDSUBENT 39 0 1042100699999 ENDENTRY 6 0 1042199999999