ENTRY 10560 20040517 00001056000000001 SUBENT 10560001 20040517 00001056000100001 BIB 10 17 1056000100002 INSTITUTE (1USAANL) 1056000100003 REFERENCE (R,ANL-NDM-16,197509) 1056000100004 AUTHOR (P.Guenther,D.Havel,A.Smith) 1056000100005 TITLE Fast neutron excitation of the ground-state rotational 1056000100006 band of 238U 1056000100007 FACILITY (DYNAM,1USAANL) Argonne tandem dynamitron 1056000100008 DETECTOR (SCIN) Proton-recoil scintillators 1056000100009 CORRECTION DAta and standard corrected for multiple scattering, 1056000100010 incident beam attenuation, and angular resolution 1056000100011 effects. 1056000100012 ERR-ANALYS (DATA-ERR) Data errors given include uncertainties 1056000100013 based upon counting statistics, normalization and 1056000100014 correction factors, and experimental resolutions. 1056000100015 STATUS No reply to author proof from author. 1056000100016 HISTORY (19760114C) 1056000100017 (19830317A) Converted to REACTION formalism 1056000100018 (20040517A) Converted to new date formats, lower case. 1056000100019 ENDBIB 17 0 1056000100020 NOCOMMON 0 0 1056000100021 ENDSUBENT 20 0 1056000199999 SUBENT 10560002 20040517 00001056000200001 BIB 6 13 1056000200002 REACTION 1((92-U-238(N,INL)92-U-238,PAR,DA)/ 1056000200003 (6-C-12(N,INL)6-C-12,PAR,DA)) 1056000200004 2(92-U-238(N,INL)92-U-238,PAR,DA) 1056000200005 INC-SPECT Incident energy spread of 10 to 15 keV. 1056000200006 SAMPLE Slab of natural uranium, 5 cm square, 1.2 cm thick, 1056000200007 oriented at 45 angular degrees to incident beam. 1056000200008 METHOD (TOF) TIme-of-flight over 2 to 6 meters 1056000200009 MONITOR 2(6-C-12(N,INL)6-C-12,,DA) 1056000200010 Constructed from carbon cross sections given in 1056000200011 ENDF/B-IV, MAT-1274 and angular distributions given 1056000200012 by Langsdorf for energies less than 1.5 MeV. 1056000200013 ERR-ANALYS2Does not include uncertainty in standard reference 1056000200014 value. 1056000200015 ENDBIB 13 0 1056000200016 COMMON 2 3 1056000200017 E-LVL ANG 1056000200018 KEV ADEG 1056000200019 45. 90. 1056000200020 ENDCOMMON 3 0 1056000200021 DATA 5 18 1056000200022 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 1056000200023 KEV NO-DIM PER-CENT B/SR PER-CENT 1056000200024 150. 0.334 20.0 0.114 20.0 1056000200025 175. 0.349 12.0 0.115 12.0 1056000200026 200. 0.305 14.0 0.099 14.0 1056000200027 225. 0.391 10.0 0.124 10.0 1056000200028 250. 0.446 12.0 0.139 12.0 1056000200029 275. 0.469 6.0 0.143 6.0 1056000200030 300. 0.523 12.0 0.157 12.0 1056000200031 325. 0.468 6.0 0.138 6.0 1056000200032 350. 0.495 7.0 0.141 7.0 1056000200033 375. 0.508 8.0 0.144 8.0 1056000200034 400. 0.489 7.0 0.136 7.0 1056000200035 425. 0.463 7.0 0.128 7.0 1056000200036 450. 0.500 8.0 0.136 8.0 1056000200037 475. 0.472 8.0 0.126 8.0 1056000200038 500. 0.545 5.0 0.140 5.0 1056000200039 535. 0.528 6.0 0.132 6.0 1056000200040 565. 0.504 5.0 0.124 5.0 1056000200041 611. 0.575 4.5 0.137 4.5 1056000200042 ENDDATA 20 0 1056000200043 ENDSUBENT 42 0 1056000299999 SUBENT 10560003 20040517 00001056000300001 BIB 9 16 1056000300002 REACTION (92-U-238(N,INL)92-U-238,PAR,SIG) 1056000300003 INC-SPECT Incident energy spread of 10 to 15 keV. 1056000300004 SAMPLE Slab of natural uranium, 5 cm square, 1.2 cm thick, 1056000300005 oriented at 45 angular degrees to incident beam. 1056000300006 METHOD (TOF) TIme-of-flight over 2 to 6 meters 1056000300007 ANALYSIS From 90. degree values,using experimentally and 1056000300008 theoretically obtained angular distributions. 1056000300009 MONITOR (6-C-12(N,INL)6-C-12,,DA) 1056000300010 Constructed from carbon cross sections given in 1056000300011 ENDF/B-IV, MAT-1274 and angular distributions given 1056000300012 by Langsdorf for energies less than 1.5 MeV. 1056000300013 CORRECTION Corrected for anisotropy. 1056000300014 ERR-ANALYS2 Does not include uncertainty in standard reference 1056000300015 value or uncertainty in anisotropy correction 1056000300016 (about 3%). 1056000300017 STATUS (DEP,10560002) 1056000300018 ENDBIB 16 0 1056000300019 COMMON 1 3 1056000300020 E-LVL 1056000300021 KEV 1056000300022 45. 1056000300023 ENDCOMMON 3 0 1056000300024 DATA 3 18 1056000300025 EN DATA DATA-ERR 1056000300026 KEV B B 1056000300027 150. 1.32 0.26 1056000300028 175. 1.33 0.16 1056000300029 200. 1.14 0.16 1056000300030 225. 1.43 0.14 1056000300031 250. 1.61 0.19 1056000300032 275. 1.65 0.10 1056000300033 300. 1.81 0.22 1056000300034 325. 1.59 0.09 1056000300035 350. 1.63 0.11 1056000300036 375. 1.66 0.13 1056000300037 400. 1.58 0.11 1056000300038 425. 1.48 0.10 1056000300039 450. 1.57 0.12 1056000300040 475. 1.45 0.12 1056000300041 500. 1.62 0.08 1056000300042 535. 1.53 0.09 1056000300043 565. 1.43 0.07 1056000300044 611. 1.58 0.07 1056000300045 ENDDATA 20 0 1056000300046 ENDSUBENT 45 0 1056000399999 SUBENT 10560004 20040517 00001056000400001 BIB 8 15 1056000400002 REACTION 1((92-U-238(N,INL)92-U-238,PAR,DA)/ 1056000400003 (6-C-12(N,INL)6-C-12,PAR,DA)) 1056000400004 2(92-U-238(N,INL)92-U-238,PAR,DA) 1056000400005 INC-SPECT Incident energy spread of 10 to 15 keV. 1056000400006 SAMPLE Small cylindrical sample of natural uranium, 2cm long, 1056000400007 and 2 cm in diameter. 1056000400008 METHOD (TOF) Time-of-flight over 5.7 meters. 1056000400009 MONITOR 2(6-C-12(N,INL)6-C-12,,DA) 1056000400010 Constructed from carbon cross sections given in 1056000400011 ENDF/B-IV, MAT-1274 and angular distributions given 1056000400012 by Langsdorf for energies less than 1.5 MeV. 1056000400013 ERR-ANALYS2 Does not include uncertainty in standard reference 1056000400014 value. 1056000400015 COMMENT 5 measurements at same energy. 1056000400016 HISTORY (19830524A) Corrected data table. 1056000400017 ENDBIB 15 0 1056000400018 COMMON 2 3 1056000400019 E-LVL ANG 1056000400020 KEV ADEG 1056000400021 45. 90. 1056000400022 ENDCOMMON 3 0 1056000400023 DATA 5 5 1056000400024 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 1056000400025 KEV NO-DIM PER-CENT B/SR PER-CENT 1056000400026 550. 0.562 7.0 0.143 7.0 1056000400027 550. 0.499 7.0 0.127 7.0 1056000400028 550. 0.618 8.0 0.157 8.0 1056000400029 550. 0.515 9.0 0.131 9.0 1056000400030 550. 0.547 9.0 0.139 9.0 1056000400031 ENDDATA 7 0 1056000400032 ENDSUBENT 31 0 1056000499999 SUBENT 10560005 20040517 00001056000500001 BIB 7 12 1056000500002 REACTION (92-U-238(N,INL)92-U-238,PAR,SIG) 1056000500003 INC-SPECT Incident energy spread of 10 to 15 keV. 1056000500004 SAMPLE Small cylindrical sample of natural uranium, 2cm long, 1056000500005 and 2 cm in diameter. 1056000500006 METHOD (TOF) Time-of-flight over 5.7 meters. 1056000500007 ANALYSIS From 90 degree data, using experimentally and 1056000500008 theoretically obtained angular distributions. 1056000500009 MONITOR (6-C-12(N,INL)6-C-12,,DA) 1056000500010 Constructed from carbon cross sections given in 1056000500011 ENDF/B-IV, MAT-1274 and angular distributions given 1056000500012 by Langsdorf for energies less than 1.5 MeV. 1056000500013 STATUS (DEP,10560004) 1056000500014 ENDBIB 12 0 1056000500015 COMMON 1 3 1056000500016 E-LVL 1056000500017 KEV 1056000500018 45. 1056000500019 ENDCOMMON 3 0 1056000500020 DATA 3 1 1056000500021 EN DATA DATA-ERR 1056000500022 KEV B B 1056000500023 550. 1.606 0.064 1056000500024 ENDDATA 3 0 1056000500025 ENDSUBENT 24 0 1056000599999 SUBENT 10560006 20040517 00001056000600001 BIB 5 9 1056000600002 REACTION (92-U-238(N,INL)92-U-238,PAR,SIG) 1056000600003 INC-SPECT Incident energy spread of 10 to 15 keV. 1056000600004 SAMPLE Cylindrical sample of natural uranium, 2 cm long, and 1056000600005 2 cm in diameter 1056000600006 METHOD (TOF) Time-of-flight over 2-3 meter path length. 1056000600007 MONITOR (6-C-12(N,INL)6-C-12,,DA) 1056000600008 Constructed from carbon cross sections given in 1056000600009 ENDF/B-IV, MAT-1274 and angular distributions given 1056000600010 by Langsdorf for energies less than 1.5 MeV. 1056000600011 ENDBIB 9 0 1056000600012 NOCOMMON 0 0 1056000600013 DATA 4 31 1056000600014 E-LVL EN DATA DATA-ERR 1056000600015 MEV MEV B B 1056000600016 0.045 0.400 1.20 0.21 1056000600017 0.045 0.450 1.52 0.22 1056000600018 0.045 0.500 1.32 0.23 1056000600019 0.045 0.550 1.70 0.18 1056000600020 0.045 0.563 1.50 0.15 1056000600021 0.045 0.669 1.56 0.15 1056000600022 0.045 0.731 1.40 0.14 1056000600023 0.045 0.766 1.29 0.13 1056000600024 0.045 0.853 1.02 0.12 1056000600025 0.045 0.955 1.23 0.15 1056000600026 0.045 1.100 0.95 0.14 1056000600027 0.045 1.200 0.61 0.12 1056000600028 0.148 0.563 0.311 0.04 1056000600029 0.148 0.669 0.416 0.04 1056000600030 0.148 0.731 0.434 0.04 1056000600031 0.148 0.766 0.425 0.04 1056000600032 0.148 0.853 0.488 0.05 1056000600033 0.148 0.955 0.533 0.08 1056000600034 0.148 1.065 0.455 0.05 1056000600035 0.148 1.122 0.533 0.05 1056000600036 0.148 1.177 0.478 0.05 1056000600037 0.148 1.222 0.414 0.06 1056000600038 0.148 1.320 0.278 0.08 1056000600039 0.148 1.397 0.321 0.05 1056000600040 0.148 1.500 0.230 0.05 1056000600041 0.308 0.840 0.025 0.012 1056000600042 0.308 0.955 0.037 0.018 1056000600043 0.308 1.100 0.070 0.030 1056000600044 0.308 1.150 0.069 0.030 1056000600045 0.308 1.200 0.072 0.050 1056000600046 0.308 1.400 0.038 0.020 1056000600047 ENDDATA 33 0 1056000600048 ENDSUBENT 47 0 1056000699999 SUBENT 10560007 20040517 00001056000700001 BIB 4 5 1056000700002 REACTION (92-U-238(N,INL)92-U-238,PAR,DA) 1056000700003 SAMPLE Cylindrical sample of natural uranium, 2 cm long, and 1056000700004 2 cm in diameter. 1056000700005 METHOD (TOF) Time-of-flight over 5.3 meter path length 1056000700006 MONITOR (1-H-1(N,EL)1-H-1,,DA) 1056000700007 ENDBIB 5 0 1056000700008 NOCOMMON 0 0 1056000700009 DATA 5 14 1056000700010 E-LVL ANG EN DATA DATA-ERR 1056000700011 MEV ADEG MEV B/SR PER-CENT 1056000700012 0.045 115. 1.8 0.054 15. 1056000700013 0.045 115. 2.4 0.022 20. 1056000700014 0.045 120. 1.5 0.049 15. 1056000700015 0.045 120. 2.1 0.033 15. 1056000700016 0.045 120. 2.7 0.024 20. 1056000700017 0.045 120. 3.0 0.025 28. 1056000700018 0.148 115. 1.8 0.016 17. 1056000700019 0.148 115. 1.8 0.021 16. 1056000700020 0.148 115. 2.4 0.008 15. 1056000700021 0.148 120. 1.5 0.025 15. 1056000700022 0.148 120. 2.1 0.019 20. 1056000700023 0.148 120. 2.7 0.006 17. 1056000700024 0.148 120. 3.0 0.008 18. 1056000700025 0.308 115. 1.8 0.006 40. 1056000700026 ENDDATA 16 0 1056000700027 ENDSUBENT 26 0 1056000799999 SUBENT 10560008 20040517 00001056000800001 BIB 6 8 1056000800002 REACTION (92-U-238(N,INL)92-U-238,PAR,SIG) 1056000800003 SAMPLE Cylindrical sample of natural uranium, 2 cm long, and 1056000800004 2 cm in diameter. 1056000800005 METHOD (TOF) Time-of-flight over 5.3 meter path length 1056000800006 MONITOR (1-H-1(N,EL)1-H-1,,DA) 1056000800007 ERR-ANALYS Do not include uncertainty in extrapolation to angle- 1056000800008 integrated values. 1056000800009 STATUS (DEP,10560007) Angle integrated data 1056000800010 ENDBIB 8 0 1056000800011 NOCOMMON 0 0 1056000800012 DATA 4 14 1056000800013 E-LVL EN DATA DATA-ERR 1056000800014 MEV MEV B B 1056000800015 0.045 1.5 0.620 0.093 1056000800016 0.045 1.8 0.706 0.105 1056000800017 0.045 2.1 0.428 0.064 1056000800018 0.045 2.4 0.317 0.063 1056000800019 0.045 2.7 0.350 0.070 1056000800020 0.045 3.0 0.390 0.115 1056000800021 0.148 1.5 0.359 0.053 1056000800022 0.148 1.8 0.237 0.040 1056000800023 0.148 1.8 0.310 0.049 1056000800024 0.148 2.1 0.311 0.062 1056000800025 0.148 2.4 0.131 0.020 1056000800026 0.148 2.7 0.120 0.020 1056000800027 0.148 3.0 0.170 0.031 1056000800028 0.308 1.8 0.075 0.030 1056000800029 ENDDATA 16 0 1056000800030 ENDSUBENT 29 0 1056000899999 ENDENTRY 8 0 1056099999999