ENTRY 10049 20170830 14351004900000001 SUBENT 10049001 20170830 14351004900100001 BIB 11 51 1004900100002 TITLE Measurements of cross sections for radiative capture 1004900100003 of 1-keV to 1-MeV neutrons by Mo, Rh, Gd, Ta, W, Re, 1004900100004 Au and U-238 1004900100005 AUTHOR (M.P.Fricke,W.M.Lopez,S.J.Friesenhahn,A.D.Carlson, 1004900100006 D.G.Costello) 1004900100007 REFERENCE (C,70HELSINKI,2,265,1970) 1004900100008 (J,NP/A,146,337,1970) 1004900100009 #doi:10.1016/0375-9474(70)90729-3 1004900100010 Neutron res.param. and radiative capture cross sections1004900100011 of Gd 1004900100012 (C,71KNOX,1,252,197103) - analysis, cross sections Mo, 1004900100013 Rh, Gd, Ta, W, Re, Au, 238U 1004900100014 (R,GA-10194,197005) - Mo, Ta, 238U cross sections 1004900100015 REL-REF (O,10211001,M.P.Fricke+,J,ANS,14,352,1971) Rh data from1004900100016 the same facility. 1004900100017 INSTITUTE (1USAGRT) 1004900100018 FACILITY (LINAC,1USAGRT) Electron linac. 1004900100019 INC-SOURCE (PHOTO) Photo-neutrons produced by 45-MeV electrons 1004900100020 on a tungsten-alloy target. Neutrons moderated in 1004900100021 lead or uranium and in polyethylene. B-10 filter used 1004900100022 to prevent overlap of low-energy neutrons from 1004900100023 different bursts. 1004900100024 SAMPLE The samples used for the capture measurements were all 1004900100025 high purity metal disks approximately 11 cm in diam. 1004900100026 and ranged in thickness from 0.1 to 0. 25 cm. Except 1004900100027 for the 238U sample which was composed of depleted 1004900100028 uranium (99.8% 238U), the isotopic composition of the 1004900100029 samples was that of the naturally occurring element. 1004900100030 DETECTOR (SCIN) Large liquid scintillator viewed by photo- 1004900100031 multipliers. 1004900100032 (HE3SP) Below 80 keV, flux determined using He3 1004900100033 proportional counters which were calibrated using 1004900100034 B-10(n,alpha) reaction. 1004900100035 (PROPC) Above 80 keV, flux determined relative to n-p 1004900100036 scattering using methane proportional counter. 1004900100037 STATUS (APRVD) Approved by author 1004900100038 (TABLE) data taken from private comm., Fricke, July 1004900100039 1970. Part of the data are presented in pdf-files 1004900100040 (see status in subents), others were received on 1004900100041 punchcards. 1004900100042 HISTORY (19700804C) 1004900100043 (19730509A) BIB changes. 1004900100044 (19810403A) Converted to reaction formalism 1004900100045 (19811120A) converted to reaction formalism 1004900100046 (19840809A) BIB corrections. 1004900100047 (19990907A) Converted to new date formalism. 1004900100048 (20120405A) SD:updated to new date formats,lower case. 1004900100049 corrected according to last EXFOR rules and dict. 1004900100050 Page in Ref. 70HELSINKI corrected. BIB update. 1004900100051 Subents 23,24 were added. 1004900100052 (20170830A) BP: BIB update, added REL-REF and doi. 1004900100053 ENDBIB 51 0 1004900100054 NOCOMMON 0 0 1004900100055 ENDSUBENT 54 0 1004900199999 SUBENT 10049002 20120405 13811004900200001 BIB 7 35 1004900200002 REACTION (42-MO-0(N,G),,SIG) 1004900200003 METHOD (TOF) Time-of-flight. 230 m flight path. 1004900200004 MONITOR (5-B-10(N,A)3-LI-7,,SIG) below 80 keV 1004900200005 (1-H-1(N,EL)1-H-1,,SIG) above 80 keV 1004900200006 CORRECTION Corrected for detection efficiency, resonance self- 1004900200007 shielding, multiple scattering. 1004900200008 Correction for finite sample effects less than 15% 1004900200009 above 5 keV. 1004900200010 ERR-ANALYS (DATA-ERR) The overall uncertainty in the shape of the 1004900200011 cross sections is obtained from the following 1004900200012 energy-dependent components: 1004900200013 * statistical and systematic uncertainties in the 1004900200014 gamma-ray counts and neutron flux data (including 1004900200015 contributions from backgrounds); 1004900200016 * an estimated 20% uncertainty in the correction 1004900200017 applied at high energies for the effect of the 1004900200018 variation of the gamma-ray pulse-height distribution1004900200019 with neutron energy; 1004900200020 * and estimated uncertainties in the corrections 1004900200021 applied for multiple scattering and resonance 1004900200022 self-shielding. 1004900200023 (ERR-1) The major uncertainties in the normalization 1004900200024 of the capture cross sections are: 1004900200025 * the uncertainty (typically < 5%) in the absolute 1004900200026 capture probability determined from the areas of 1004900200027 resolved resonances; 1004900200028 * a 5% uncertainty from systematic errors in the flux 1004900200029 measurements; 1004900200030 * and an uncertainty (~ 5%) in the gamma-ray yield 1004900200031 at the matching region 2-8 keV due to a 20% 1004900200032 uncertainty in the determination of background 1004900200033 caused by neutrons scattered from the sample. 1004900200034 COMMENT From compiler: Value of uncertainty was taken from the 1004900200035 letter of the author. 1004900200036 STATUS (TABLE) Tbl.2 from report GA-10194,1970 1004900200037 ENDBIB 35 0 1004900200038 COMMON 1 3 1004900200039 ERR-1 1004900200040 PER-CENT 1004900200041 25. 1004900200042 ENDCOMMON 3 0 1004900200043 DATA 3 95 1004900200044 EN DATA DATA-ERR 1004900200045 KEV B PER-CENT 1004900200046 .9576 .233 21. 1004900200047 1.009 .539 21. 1004900200048 1.064 .541 21. 1004900200049 1.124 .600 21. 1004900200050 1.190 .534 21. 1004900200051 1.253 .515 20. 1004900200052 1.321 .338 20. 1004900200053 1.393 .574 19. 1004900200054 1.469 .417 19. 1004900200055 1.553 .850 18. 1004900200056 1.645 .327 18. 1004900200057 1.745 .694 17. 1004900200058 1.843 .335 17. 1004900200059 1.941 .536 16. 1004900200060 2.046 .476 16. 1004900200061 2.161 .694 16. 1004900200062 2.285 .421 16. 1004900200063 2.420 .567 16. 1004900200064 2.568 .456 15. 1004900200065 2.730 .327 15. 1004900200066 2.890 .274 15. 1004900200067 3.044 .410 15. 1004900200068 3.209 .826 15. 1004900200069 3.393 .382 15. 1004900200070 3.588 .352 15. 1004900200071 3.800 .454 15. 1004900200072 4.036 .279 14. 1004900200073 4.290 .442 14. 1004900200074 4.569 .410 14. 1004900200075 4.877 .449 14. 1004900200076 5.171 .259 14. 1004900200077 5.451 .408 13. 1004900200078 5.748 .386 13. 1004900200079 6.070 .472 13. 1004900200080 6.420 .296 13. 1004900200081 6.807 .348 13. 1004900200082 7.226 .322 13. 1004900200083 7.690 .302 13. 1004900200084 8.191 .264 13. 1004900200085 8.743 .340 12. 1004900200086 9.362 .257 12. 1004900200087 10.04 .289 12. 1004900200088 10.80 .267 13. 1004900200089 11.50 .222 13. 1004900200090 12.12 .233 14. 1004900200091 12.77 .193 14. 1004900200092 13.48 .190 15. 1004900200093 14.26 .195 15. 1004900200094 15.10 .194 15. 1004900200095 16.02 .188 14. 1004900200096 17.03 .165 14. 1004900200097 18.14 .199 14. 1004900200098 19.35 .172 14. 1004900200099 20.70 .154 13. 1004900200100 22.19 .138 13. 1004900200101 23.86 .132 13. 1004900200102 25.70 .145 12. 1004900200103 27.77 .137 12. 1004900200104 30.12 .129 13. 1004900200105 32.78 .126 13. 1004900200106 35.78 .111 13. 1004900200107 39.23 .106 13. 1004900200108 43.19 .099 14. 1004900200109 46.57 .0940 14. 1004900200110 49.01 .0921 14. 1004900200111 51.72 .0825 14. 1004900200112 54.64 .0840 14. 1004900200113 57.82 .0835 14. 1004900200114 61.22 .0829 14. 1004900200115 64.99 .0753 14. 1004900200116 69.12 .0740 14. 1004900200117 73.65 .0687 14. 1004900200118 78.63 .0616 14. 1004900200119 84.22 .0690 14. 1004900200120 90.32 .0692 13. 1004900200121 97.10 .0628 13. 1004900200122 104.7 .0547 12. 1004900200123 113.3 .0544 12. 1004900200124 123.0 .0543 12. 1004900200125 133.8 .0446 12. 1004900200126 146.3 .0497 11. 1004900200127 160.6 .0446 11. 1004900200128 176.9 .0438 11. 1004900200129 196.1 .0381 10. 1004900200130 218.5 .0375 9. 1004900200131 245.1 .0379 8. 1004900200132 276.5 .0372 7. 1004900200133 314.7 .0374 6. 1004900200134 361.4 .0346 6. 1004900200135 418.8 .0354 5. 1004900200136 491.7 .0356 5. 1004900200137 585.2 .0319 4. 1004900200138 708.5 .0311 4. 1004900200139 835.5 .0265 4. 1004900200140 1107.5 .0215 9. 1004900200141 ENDDATA 97 0 1004900200142 ENDSUBENT 141 0 1004900299999 SUBENT 10049003 20120405 13811004900300001 BIB 6 33 1004900300002 REACTION (64-GD-0(N,G),,SIG) 1004900300003 METHOD (TOF) Time-of-flight. 230 m flight path. 1004900300004 MONITOR (5-B-10(N,A)3-LI-7,,SIG) Below 80 keV. 1004900300005 (1-H-1(N,EL)1-H-1,,SIG) Above 80 keV. 1004900300006 CORRECTION Corrected for detection efficiency, resonance self- 1004900300007 shielding, multiple scattering. 1004900300008 Correction for finite sample effects less than 15% 1004900300009 above 5 keV. 1004900300010 ERR-ANALYS (DATA-ERR) The overall uncertainty in the shape of the 1004900300011 cross sections is obtained from the following 1004900300012 energy-dependent components: 1004900300013 * statistical and systematic uncertainties in the 1004900300014 gamma-ray counts and neutron flux data (including 1004900300015 contributions from backgrounds); 1004900300016 * an estimated 20% uncertainty in the correction 1004900300017 applied at high energies for the effect of the 1004900300018 variation of the gamma-ray pulse-height distribution1004900300019 with neutron energy; 1004900300020 * and estimated uncertainties in the corrections 1004900300021 applied for multiple scattering and resonance 1004900300022 self-shielding. 1004900300023 (ERR-1) The major uncertainties in the normalization 1004900300024 of the capture cross sections are: 1004900300025 * the uncertainty (typically < 5%) in the absolute 1004900300026 capture probability determined from the areas of 1004900300027 resolved resonances; 1004900300028 * a 5% uncertainty from systematic errors in the flux 1004900300029 measurements; 1004900300030 * and an uncertainty (~ 5%) in the gamma-ray yield 1004900300031 at the matching region 2-8 keV due to a 20% 1004900300032 uncertainty in the determination of background 1004900300033 caused by neutrons scattered from the sample. 1004900300034 STATUS (TABLE) data from priv.com. in pdf-file. 1004900300035 ENDBIB 33 0 1004900300036 COMMON 1 3 1004900300037 ERR-1 1004900300038 PER-CENT 1004900300039 10. 1004900300040 ENDCOMMON 3 0 1004900300041 DATA 3 89 1004900300042 EN DATA DATA-ERR 1004900300043 KEV B PER-CENT 1004900300044 1.005 5.43 5. 1004900300045 1.060 8.17 5. 1004900300046 1.120 6.97 5. 1004900300047 1.185 7.11 5. 1004900300048 1.250 7.01 5. 1004900300049 1.316 6.13 5. 1004900300050 1.387 6.50 5. 1004900300051 1.463 6.92 5. 1004900300052 1.547 6.22 5. 1004900300053 1.637 6.52 5. 1004900300054 1.736 5.55 5. 1004900300055 1.834 5.68 5. 1004900300056 2.274 4.34 5. 1004900300057 2.408 4.55 5. 1004900300058 2.555 4.18 5. 1004900300059 2.873 3.42 5. 1004900300060 3.026 3.24 5. 1004900300061 3.190 4.09 5. 1004900300062 3.369 2.94 5. 1004900300063 3.563 3.16 5. 1004900300064 3.774 2.93 5. 1004900300065 4.004 2.85 5. 1004900300066 4.256 3.36 6. 1004900300067 4.533 2.59 6. 1004900300068 4.838 2.19 6. 1004900300069 5.130 2.56 6. 1004900300070 5.402 2.57 6. 1004900300071 5.697 2.19 6. 1004900300072 6.016 2.44 6. 1004900300073 6.363 2.07 6. 1004900300074 6.741 2.08 6. 1004900300075 7.154 2.30 6. 1004900300076 7.606 1.88 6. 1004900300077 8.102 1.78 6. 1004900300078 8.648 1.69 6. 1004900300079 9.251 1.58 6. 1004900300080 9.920 1.70 6. 1004900300081 10.66 1.60 6. 1004900300082 11.35 1.48 6. 1004900300083 11.95 1.68 6. 1004900300084 12.59 1.12 6. 1004900300085 13.29 1.45 6. 1004900300086 14.05 1.23 5. 1004900300087 14.88 1.29 5. 1004900300088 15.78 1.34 5. 1004900300089 16.76 1.20 5. 1004900300090 17.85 1.32 5. 1004900300091 19.03 1.20 5. 1004900300092 20.35 1.22 5. 1004900300093 21.80 1.09 5. 1004900300094 23.42 1.01 5. 1004900300095 25.22 1.10 5. 1004900300096 27.23 1.03 5. 1004900300097 29.50 .895 5. 1004900300098 32.07 .922 5. 1004900300099 34.98 .929 6. 1004900300100 38.31 .922 6. 1004900300101 42.14 .803 6. 1004900300102 45.39 .875 6. 1004900300103 47.77 .791 6. 1004900300104 50.36 .761 6. 1004900300105 53.15 .628 6. 1004900300106 56.19 .722 6. 1004900300107 59.49 .599 6. 1004900300108 63.10 .650 5. 1004900300109 67.04 .639 5. 1004900300110 71.37 .617 5. 1004900300111 76.12 .503 5. 1004900300112 81.37 .626 4. 1004900300113 87.18 .538 4. 1004900300114 93.64 .488 4. 1004900300115 100.8 .493 4. 1004900300116 108.9 .441 3. 1004900300117 118.0 .373 3. 1004900300118 128.2 .359 3. 1004900300119 139.9 .381 3. 1004900300120 153.2 .328 3. 1004900300121 168.5 .339 3. 1004900300122 186.2 .325 3. 1004900300123 206.9 .282 2. 1004900300124 231.2 .299 2. 1004900300125 260.1 .244 2. 1004900300126 294.7 .249 2. 1004900300127 336.8 .234 2. 1004900300128 388.5 .205 2. 1004900300129 453.2 .194 2. 1004900300130 535.4 .167 2. 1004900300131 642.3 .151 2. 1004900300132 752.0 .137 2. 1004900300133 ENDDATA 91 0 1004900300134 ENDSUBENT 133 0 1004900399999 SUBENT 10049004 20120405 13811004900400001 BIB 6 33 1004900400002 REACTION (73-TA-0(N,G),,SIG) 1004900400003 METHOD (TOF) Time-of-flight. 230 m flight path. 1004900400004 MONITOR (5-B-10(N,A)3-LI-7,,SIG) Below 80 keV 1004900400005 (1-H-1(N,EL)1-H-1,,SIG) above 80 keV 1004900400006 CORRECTION Corrected for detection efficiency, resonance self- 1004900400007 shielding, multiple scattering. 1004900400008 Correction for finite sample effects less than 15% 1004900400009 above 5 keV. 1004900400010 ERR-ANALYS (DATA-ERR) The overall uncertainty in the shape of the 1004900400011 cross sections is obtained from the following 1004900400012 energy-dependent components: 1004900400013 * statistical and systematic uncertainties in the 1004900400014 gamma-ray counts and neutron flux data (including 1004900400015 contributions from backgrounds); 1004900400016 * an estimated 20% uncertainty in the correction 1004900400017 applied at high energies for the effect of the 1004900400018 variation of the gamma-ray pulse-height distribution1004900400019 with neutron energy; 1004900400020 * and estimated uncertainties in the corrections 1004900400021 applied for multiple scattering and resonance 1004900400022 self-shielding. 1004900400023 (ERR-1) The major uncertainties in the normalization 1004900400024 of the capture cross sections are: 1004900400025 * the uncertainty (typically < 5%) in the absolute 1004900400026 capture probability determined from the areas of 1004900400027 resolved resonances; 1004900400028 * a 5% uncertainty from systematic errors in the flux 1004900400029 measurements; 1004900400030 * and an uncertainty (~ 5%) in the gamma-ray yield 1004900400031 at the matching region 2-8 keV due to a 20% 1004900400032 uncertainty in the determination of background 1004900400033 caused by neutrons scattered from the sample. 1004900400034 STATUS (TABLE) Tbl.1 from report GA-10194,1970 1004900400035 ENDBIB 33 0 1004900400036 COMMON 1 3 1004900400037 ERR-1 1004900400038 PER-CENT 1004900400039 10. 1004900400040 ENDCOMMON 3 0 1004900400041 DATA 3 95 1004900400042 EN DATA DATA-ERR 1004900400043 KEV B PER-CENT 1004900400044 .9576 12.6 12. 1004900400045 1.009 8.52 11. 1004900400046 1.064 9.92 11. 1004900400047 1.124 7.65 10. 1004900400048 1.190 8.70 10. 1004900400049 1.253 8.03 10. 1004900400050 1.321 8.91 10. 1004900400051 1.393 6.99 10. 1004900400052 1.469 4.79 10. 1004900400053 1.553 6.30 10. 1004900400054 1.645 6.93 9. 1004900400055 1.745 6.43 9. 1004900400056 1.843 5.17 9. 1004900400057 1.941 4.40 9. 1004900400058 2.046 5.58 9. 1004900400059 2.161 5.68 9. 1004900400060 2.285 5.38 9. 1004900400061 2.420 4.61 9. 1004900400062 2.568 4.96 9. 1004900400063 2.730 4.06 9. 1004900400064 2.890 3.55 9. 1004900400065 3.044 3.86 9. 1004900400066 3.209 3.54 9. 1004900400067 3.393 3.53 9. 1004900400068 3.588 3.46 9. 1004900400069 3.800 3.45 9. 1004900400070 4.036 2.90 9. 1004900400071 4.290 3.40 9. 1004900400072 4.569 2.53 9. 1004900400073 4.877 2.82 9. 1004900400074 5.171 2.16 9. 1004900400075 5.451 2.62 8. 1004900400076 5.748 2.77 8. 1004900400077 6.070 2.52 8. 1004900400078 6.420 2.30 8. 1004900400079 6.807 2.12 8. 1004900400080 7.226 2.10 8. 1004900400081 7.690 2.17 8. 1004900400082 8.191 1.98 8. 1004900400083 8.743 1.89 8. 1004900400084 9.362 1.74 8. 1004900400085 10.04 1.73 8. 1004900400086 10.80 1.69 8. 1004900400087 11.50 1.66 8. 1004900400088 12.12 1.57 8. 1004900400089 12.77 1.54 8. 1004900400090 13.48 1.51 8. 1004900400091 14.26 1.27 8. 1004900400092 15.10 1.20 8. 1004900400093 16.02 1.31 8. 1004900400094 17.03 1.23 8. 1004900400095 18.14 1.26 8. 1004900400096 19.35 1.14 8. 1004900400097 20.70 1.11 8. 1004900400098 22.19 1.11 8. 1004900400099 23.86 1.10 8. 1004900400100 25.70 .988 8. 1004900400101 27.77 .943 8. 1004900400102 30.12 .876 8. 1004900400103 32.78 .811 8. 1004900400104 35.78 .800 8. 1004900400105 39.23 .743 8. 1004900400106 43.19 .720 8. 1004900400107 46.57 .625 8. 1004900400108 49.01 .706 8. 1004900400109 51.72 .596 8. 1004900400110 54.64 .601 8. 1004900400111 57.82 .646 7. 1004900400112 61.22 .594 7. 1004900400113 64.99 .614 7. 1004900400114 69.12 .502 7. 1004900400115 73.65 .512 7. 1004900400116 78.63 .527 7. 1004900400117 84.22 .539 7. 1004900400118 90.32 .437 7. 1004900400119 97.10 .484 7. 1004900400120 104.7 .472 7. 1004900400121 113.3 .450 7. 1004900400122 123.0 .423 7. 1004900400123 133.8 .389 7. 1004900400124 146.3 .340 6. 1004900400125 160.6 .328 6. 1004900400126 176.9 .317 6. 1004900400127 196.1 .310 6. 1004900400128 218.5 .296 5. 1004900400129 245.1 .290 5. 1004900400130 276.5 .258 5. 1004900400131 314.7 .252 5. 1004900400132 361.4 .220 5. 1004900400133 418.8 .205 5. 1004900400134 491.7 .201 4. 1004900400135 585.2 .174 4. 1004900400136 708.5 .163 5. 1004900400137 835.5 .142 4. 1004900400138 1107.5 .124 9. 1004900400139 ENDDATA 97 0 1004900400140 ENDSUBENT 139 0 1004900499999 SUBENT 10049005 20120405 13811004900500001 BIB 5 32 1004900500002 REACTION (74-W-0(N,G),,SIG) 1004900500003 METHOD (TOF) Time-of-flight. 230 m flight path. 1004900500004 MONITOR (5-B-10(N,A)3-LI-7,,SIG) Below 80 keV 1004900500005 (1-H-1(N,EL)1-H-1,,SIG) above 80 keV. 1004900500006 CORRECTION Corrected for detection efficiency, resonance self- 1004900500007 shielding, multiple scattering. 1004900500008 Correction for finite sample effects less than 15% 1004900500009 above 5 keV. 1004900500010 ERR-ANALYS (DATA-ERR) The overall uncertainty in the shape of the 1004900500011 cross sections is obtained from the following 1004900500012 energy-dependent components: 1004900500013 * statistical and systematic uncertainties in the 1004900500014 gamma-ray counts and neutron flux data (including 1004900500015 contributions from backgrounds); 1004900500016 * an estimated 20% uncertainty in the correction 1004900500017 applied at high energies for the effect of the 1004900500018 variation of the gamma-ray pulse-height distribution1004900500019 with neutron energy; 1004900500020 * and estimated uncertainties in the corrections 1004900500021 applied for multiple scattering and resonance 1004900500022 self-shielding. 1004900500023 (ERR-1) The major uncertainties in the normalization 1004900500024 of the capture cross sections are: 1004900500025 * the uncertainty (typically < 5%) in the absolute 1004900500026 capture probability determined from the areas of 1004900500027 resolved resonances; 1004900500028 * a 5% uncertainty from systematic errors in the flux 1004900500029 measurements; 1004900500030 * and an uncertainty (~ 5%) in the gamma-ray yield 1004900500031 at the matching region 2-8 keV due to a 20% 1004900500032 uncertainty in the determination of background 1004900500033 caused by neutrons scattered from the sample. 1004900500034 ENDBIB 32 0 1004900500035 COMMON 1 3 1004900500036 ERR-1 1004900500037 PER-CENT 1004900500038 25. 1004900500039 ENDCOMMON 3 0 1004900500040 DATA 3 92 1004900500041 EN DATA DATA-ERR 1004900500042 KEV B PER-CENT 1004900500043 1.005 3.04 10. 1004900500044 1.060 1.92 10. 1004900500045 1.120 3.56 10. 1004900500046 1.185 2.03 10. 1004900500047 1.250 1.47 10. 1004900500048 1.316 1.63 10. 1004900500049 1.387 1.67 9. 1004900500050 1.463 1.38 9. 1004900500051 1.547 1.67 10. 1004900500052 1.637 1.24 9. 1004900500053 1.736 1.18 9. 1004900500054 1.834 1.60 9. 1004900500055 1.931 1.26 9. 1004900500056 2.036 1.62 9. 1004900500057 2.150 1.60 9. 1004900500058 2.274 1.37 9. 1004900500059 2.408 1.17 9. 1004900500060 2.555 1.24 8. 1004900500061 2.716 .941 9. 1004900500062 2.873 1.09 9. 1004900500063 3.026 1.09 9. 1004900500064 3.190 1.06 9. 1004900500065 3.369 .949 9. 1004900500066 3.563 .944 9. 1004900500067 3.744 .773 9. 1004900500068 4.004 .922 9. 1004900500069 4.256 .927 9. 1004900500070 4.533 .787 9. 1004900500071 4.838 .760 9. 1004900500072 5.130 .711 9. 1004900500073 5.402 .621 9. 1004900500074 5.697 .687 9. 1004900500075 6.016 .709 9. 1004900500076 6.363 .638 9. 1004900500077 6.741 .584 9. 1004900500078 7.154 .670 8. 1004900500079 7.606 .585 8. 1004900500080 8.102 .537 8. 1004900500081 8.648 .503 8. 1004900500082 9.251 .500 8. 1004900500083 9.920 .472 8. 1004900500084 10.66 .456 8. 1004900500085 11.35 .421 8. 1004900500086 11.95 .386 8. 1004900500087 12.59 .376 8. 1004900500088 13.29 .421 8. 1004900500089 14.05 .398 8. 1004900500090 14.88 .337 8. 1004900500091 15.78 .372 8. 1004900500092 16.76 .357 8. 1004900500093 17.85 .366 8. 1004900500094 19.03 .322 8. 1004900500095 20.35 .320 8. 1004900500096 21.80 .296 8. 1004900500097 23.42 .283 8. 1004900500098 25.22 .295 8. 1004900500099 27.23 .261 8. 1004900500100 29.50 .261 8. 1004900500101 32.07 .250 8. 1004900500102 34.98 .229 8. 1004900500103 38.31 .245 8. 1004900500104 42.14 .201 8. 1004900500105 45.39 .207 8. 1004900500106 47.77 .236 8. 1004900500107 50.36 .202 8. 1004900500108 53.15 .166 8. 1004900500109 56.19 .186 8. 1004900500110 59.49 .194 8. 1004900500111 63.10 .178 8. 1004900500112 67.04 .169 7. 1004900500113 71.37 .188 7. 1004900500114 76.12 .199 7. 1004900500115 81.37 .187 7. 1004900500116 87.18 .179 7. 1004900500117 93.64 .154 7. 1004900500118 100.8 .177 6. 1004900500119 108.9 .147 6. 1004900500120 118.0 .128 6. 1004900500121 128.2 .125 6. 1004900500122 139.9 .105 6. 1004900500123 153.2 .101 5. 1004900500124 168.5 .0963 5. 1004900500125 186.2 .0912 5. 1004900500126 206.9 .0838 5. 1004900500127 231.2 .0735 5. 1004900500128 260.1 .0669 4. 1004900500129 294.7 .0621 4. 1004900500130 336.8 .0584 4. 1004900500131 388.5 .0536 3. 1004900500132 453.2 .0495 3. 1004900500133 535.4 .0450 4. 1004900500134 642.3 .0466 3. 1004900500135 ENDDATA 94 0 1004900500136 ENDSUBENT 135 0 1004900599999 SUBENT 10049006 20120405 13811004900600001 BIB 5 32 1004900600002 REACTION (75-RE-0(N,G),,SIG) 1004900600003 METHOD (TOF) Time-of-flight. 230 m flight path. 1004900600004 MONITOR (5-B-10(N,A)3-LI-7,,SIG) Below 80 keV, 1004900600005 (1-H-1(N,EL)1-H-1,,SIG) above 80 keV. 1004900600006 CORRECTION Corrected for detection efficiency, resonance self- 1004900600007 shielding, multiple scattering. 1004900600008 Correction for finite sample effects less than 15% 1004900600009 above 5 keV. 1004900600010 ERR-ANALYS (DATA-ERR) The overall uncertainty in the shape of the 1004900600011 cross sections is obtained from the following 1004900600012 energy-dependent components: 1004900600013 * statistical and systematic uncertainties in the 1004900600014 gamma-ray counts and neutron flux data (including 1004900600015 contributions from backgrounds); 1004900600016 * an estimated 20% uncertainty in the correction 1004900600017 applied at high energies for the effect of the 1004900600018 variation of the gamma-ray pulse-height distribution1004900600019 with neutron energy; 1004900600020 * and estimated uncertainties in the corrections 1004900600021 applied for multiple scattering and resonance 1004900600022 self-shielding. 1004900600023 (ERR-1) The major uncertainties in the normalization 1004900600024 of the capture cross sections are: 1004900600025 * the uncertainty (typically < 5%) in the absolute 1004900600026 capture probability determined from the areas of 1004900600027 resolved resonances; 1004900600028 * a 5% uncertainty from systematic errors in the flux 1004900600029 measurements; 1004900600030 * and an uncertainty (~ 5%) in the gamma-ray yield 1004900600031 at the matching region 2-8 keV due to a 20% 1004900600032 uncertainty in the determination of background 1004900600033 caused by neutrons scattered from the sample. 1004900600034 ENDBIB 32 0 1004900600035 COMMON 1 3 1004900600036 ERR-1 1004900600037 PER-CENT 1004900600038 10. 1004900600039 ENDCOMMON 3 0 1004900600040 DATA 3 92 1004900600041 EN DATA DATA-ERR 1004900600042 KEV B PER-CENT 1004900600043 1.005 11.31 6. 1004900600044 1.060 12.33 6. 1004900600045 1.120 11.80 6. 1004900600046 1.185 13.00 6. 1004900600047 1.250 10.32 6. 1004900600048 1.316 11.30 6. 1004900600049 1.387 12.25 6. 1004900600050 1.463 10.38 6. 1004900600051 1.547 11.79 6. 1004900600052 1.637 7.47 6. 1004900600053 1.736 8.63 6. 1004900600054 1.834 9.37 6. 1004900600055 1.931 7.61 6. 1004900600056 2.036 7.38 5. 1004900600057 2.150 8.07 5. 1004900600058 2.274 7.44 5. 1004900600059 2.408 5.75 5. 1004900600060 2.555 7.07 5. 1004900600061 2.716 6.38 5. 1004900600062 2.873 5.86 6. 1004900600063 3.026 6.09 6. 1004900600064 3.190 5.75 6. 1004900600065 3.369 5.82 6. 1004900600066 3.563 5.63 6. 1004900600067 3.774 4.67 6. 1004900600068 4.004 4.52 6. 1004900600069 4.256 4.60 6. 1004900600070 4.533 4.36 7. 1004900600071 4.838 4.82 7. 1004900600072 5.130 3.81 7. 1004900600073 5.402 3.51 7. 1004900600074 5.697 3.67 7. 1004900600075 6.016 3.54 7. 1004900600076 6.363 3.72 7. 1004900600077 6.741 3.01 7. 1004900600078 7.154 3.90 8. 1004900600079 7.606 3.05 8. 1004900600080 8.102 2.97 8. 1004900600081 8.648 2.63 8. 1004900600082 9.251 2.52 8. 1004900600083 9.920 2.73 8. 1004900600084 10.66 2.65 8. 1004900600085 11.35 2.11 8. 1004900600086 11.95 2.13 8. 1004900600087 12.59 2.12 8. 1004900600088 13.29 2.06 8. 1004900600089 14.05 1.79 9. 1004900600090 14.88 1.97 9. 1004900600091 15.78 1.78 9. 1004900600092 16.76 1.66 9. 1004900600093 17.85 1.74 9. 1004900600094 19.03 1.44 9. 1004900600095 20.35 1.35 9. 1004900600096 21.80 1.51 9. 1004900600097 23.42 1.24 9. 1004900600098 25.22 1.24 9. 1004900600099 27.23 1.34 10. 1004900600100 29.50 1.16 10. 1004900600101 32.07 1.08 10. 1004900600102 34.98 1.02 10. 1004900600103 38.31 .943 10. 1004900600104 42.14 .905 10. 1004900600105 45.39 .953 10. 1004900600106 47.77 .936 10. 1004900600107 50.36 .878 10. 1004900600108 53.15 .774 10. 1004900600109 56.19 .746 10. 1004900600110 59.49 .707 9. 1004900600111 63.10 .857 9. 1004900600112 67.04 .828 9. 1004900600113 71.37 .806 9. 1004900600114 76.12 .738 8. 1004900600115 81.37 .778 8. 1004900600116 87.18 .690 8. 1004900600117 93.64 .721 7. 1004900600118 100.8 .786 7. 1004900600119 108.9 .647 7. 1004900600120 118.0 .590 7. 1004900600121 128.2 .623 7. 1004900600122 139.9 .658 6. 1004900600123 153.2 .596 6. 1004900600124 168.5 .523 6. 1004900600125 186.2 .528 6. 1004900600126 206.9 .519 5. 1004900600127 231.2 .475 5. 1004900600128 260.1 .417 4. 1004900600129 294.7 .402 4. 1004900600130 336.8 .370 3. 1004900600131 388.5 .362 3. 1004900600132 453.2 .316 4. 1004900600133 535.4 .284 4. 1004900600134 642.3 .288 3. 1004900600135 ENDDATA 94 0 1004900600136 ENDSUBENT 135 0 1004900699999 SUBENT 10049007 20120405 13811004900700001 BIB 5 32 1004900700002 REACTION (79-AU-197(N,G)79-AU-198,,SIG) 1004900700003 METHOD (TOF) Time-of-flight. 230 m flight path. 1004900700004 MONITOR (5-B-10(N,A)3-LI-7,,SIG) Below 80 keV, 1004900700005 (1-H-1(N,EL)1-H-1,,SIG) above 80 keV. 1004900700006 CORRECTION Corrected for detection efficiency, resonance self- 1004900700007 shielding, multiple scattering. 1004900700008 Correction for finite sample effects less than 15% 1004900700009 above 5 keV. 1004900700010 ERR-ANALYS (DATA-ERR) The overall uncertainty in the shape of the 1004900700011 cross sections is obtained from the following 1004900700012 energy-dependent components: 1004900700013 * statistical and systematic uncertainties in the 1004900700014 gamma-ray counts and neutron flux data (including 1004900700015 contributions from backgrounds); 1004900700016 * an estimated 20% uncertainty in the correction 1004900700017 applied at high energies for the effect of the 1004900700018 variation of the gamma-ray pulse-height distribution1004900700019 with neutron energy; 1004900700020 * and estimated uncertainties in the corrections 1004900700021 applied for multiple scattering and resonance 1004900700022 self-shielding. 1004900700023 (ERR-1) The major uncertainties in the normalization 1004900700024 of the capture cross sections are: 1004900700025 * the uncertainty (typically < 5%) in the absolute 1004900700026 capture probability determined from the areas of 1004900700027 resolved resonances; 1004900700028 * a 5% uncertainty from systematic errors in the flux 1004900700029 measurements; 1004900700030 * and an uncertainty (~ 5%) in the gamma-ray yield 1004900700031 at the matching region 2-8 keV due to a 20% 1004900700032 uncertainty in the determination of background 1004900700033 caused by neutrons scattered from the sample. 1004900700034 ENDBIB 32 0 1004900700035 COMMON 1 3 1004900700036 ERR-1 1004900700037 PER-CENT 1004900700038 10. 1004900700039 ENDCOMMON 3 0 1004900700040 DATA 3 95 1004900700041 EN DATA DATA-ERR 1004900700042 KEV B PER-CENT 1004900700043 .9576 5.53 21. 1004900700044 1.007 9.21 20. 1004900700045 1.064 7.02 19. 1004900700046 1.124 6.54 18. 1004900700047 1.190 6.84 17. 1004900700048 1.253 7.03 16. 1004900700049 1.321 6.87 15. 1004900700050 1.393 6.43 15. 1004900700051 1.469 6.76 14. 1004900700052 1.553 3.99 14. 1004900700053 1.645 3.92 14. 1004900700054 1.745 5.35 14. 1004900700055 1.843 4.24 13. 1004900700056 1.941 3.57 13. 1004900700057 2.046 5.10 12. 1004900700058 2.161 4.38 12. 1004900700059 2.285 3.06 12. 1004900700060 2.420 3.51 11. 1004900700061 2.568 3.28 11. 1004900700062 2.730 2.73 10. 1004900700063 2.890 2.84 10. 1004900700064 3.044 2.58 9. 1004900700065 3.209 2.14 9. 1004900700066 3.393 2.72 9. 1004900700067 3.588 2.76 9. 1004900700068 3.800 2.64 9. 1004900700069 4.036 2.91 8. 1004900700070 4.290 2.62 8. 1004900700071 4.569 1.92 7. 1004900700072 4.877 2.11 7. 1004900700073 5.171 2.10 7. 1004900700074 5.451 2.00 8. 1004900700075 5.748 2.05 8. 1004900700076 6.070 2.19 8. 1004900700077 6.420 1.68 8. 1004900700078 6.807 1.81 8. 1004900700079 7.226 1.97 8. 1004900700080 7.690 1.56 8. 1004900700081 8.191 1.53 7. 1004900700082 8.743 1.45 7. 1004900700083 9.362 1.23 8. 1004900700084 10.04 1.39 8. 1004900700085 10.80 1.10 9. 1004900700086 11.50 1.19 9. 1004900700087 12.12 1.17 9. 1004900700088 12.77 1.06 10. 1004900700089 13.48 .935 10. 1004900700090 14.26 .947 10. 1004900700091 15.10 1.01 9. 1004900700092 16.02 .870 9. 1004900700093 17.03 .835 9. 1004900700094 18.14 .950 8. 1004900700095 19.35 .810 8. 1004900700096 20.70 .785 8. 1004900700097 21.80 .722 9. 1004900700098 23.42 .682 9. 1004900700099 25.22 .676 9. 1004900700100 27.23 .636 9. 1004900700101 29.50 .596 9. 1004900700102 32.78 .584 9. 1004900700103 35.78 .550 10. 1004900700104 39.23 .520 10. 1004900700105 43.19 .482 10. 1004900700106 46.57 .495 10. 1004900700107 49.01 .486 10. 1004900700108 51.72 .453 9. 1004900700109 54.64 .439 9. 1004900700110 57.82 .451 9. 1004900700111 61.22 .428 8. 1004900700112 64.99 .430 8. 1004900700113 69.12 .400 8. 1004900700114 73.65 .365 8. 1004900700115 78.63 .373 8. 1004900700116 84.22 .376 7. 1004900700117 90.32 .379 7. 1004900700118 97.10 .327 7. 1004900700119 104.7 .323 7. 1004900700120 113.3 .330 7. 1004900700121 123.0 .311 6. 1004900700122 133.8 .335 6. 1004900700123 146.3 .295 6. 1004900700124 160.6 .279 5. 1004900700125 176.9 .278 5. 1004900700126 196.1 .261 5. 1004900700127 218.5 .267 5. 1004900700128 245.1 .255 4. 1004900700129 276.5 .244 4. 1004900700130 314.7 .212 4. 1004900700131 361.4 .181 4. 1004900700132 418.8 .173 4. 1004900700133 491.7 .159 4. 1004900700134 585.2 .128 4. 1004900700135 708.5 .106 4. 1004900700136 835.5 .091 5. 1004900700137 1107.5 .082 10. 1004900700138 ENDDATA 97 0 1004900700139 ENDSUBENT 138 0 1004900799999 SUBENT 10049008 20120405 13811004900800001 BIB 5 32 1004900800002 REACTION (92-U-238(N,G)92-U-239,,SIG) 1004900800003 METHOD (TOF) Time-of-flight. 230 m flight path. 1004900800004 MONITOR (5-B-10(N,A)3-LI-7,,SIG) Below 80 keV 1004900800005 (1-H-1(N,EL)1-H-1,,SIG) above 80 keV. 1004900800006 CORRECTION Corrected for detection efficiency, resonance self- 1004900800007 shielding, multiple scattering. 1004900800008 Correction for finite sample effects less than 15% 1004900800009 above 5 keV. 1004900800010 ERR-ANALYS (DATA-ERR) The overall uncertainty in the shape of the 1004900800011 cross sections is obtained from the following 1004900800012 energy-dependent components: 1004900800013 * statistical and systematic uncertainties in the 1004900800014 gamma-ray counts and neutron flux data (including 1004900800015 contributions from backgrounds); 1004900800016 * an estimated 20% uncertainty in the correction 1004900800017 applied at high energies for the effect of the 1004900800018 variation of the gamma-ray pulse-height distribution1004900800019 with neutron energy; 1004900800020 * and estimated uncertainties in the corrections 1004900800021 applied for multiple scattering and resonance 1004900800022 self-shielding. 1004900800023 (ERR-1) The major uncertainties in the normalization 1004900800024 of the capture cross sections are: 1004900800025 * the uncertainty (typically < 5%) in the absolute 1004900800026 capture probability determined from the areas of 1004900800027 resolved resonances; 1004900800028 * a 5% uncertainty from systematic errors in the flux 1004900800029 measurements; 1004900800030 * and an uncertainty (~ 5%) in the gamma-ray yield 1004900800031 at the matching region 2-8 keV due to a 20% 1004900800032 uncertainty in the determination of background 1004900800033 caused by neutrons scattered from the sample. 1004900800034 ENDBIB 32 0 1004900800035 COMMON 1 3 1004900800036 ERR-1 1004900800037 PER-CENT 1004900800038 10. 1004900800039 ENDCOMMON 3 0 1004900800040 DATA 3 93 1004900800041 EN DATA DATA-ERR 1004900800042 KEV B PER-CENT 1004900800043 1.005 1.73 12. 1004900800044 1.060 1.79 12. 1004900800045 1.120 3.15 12. 1004900800046 1.185 3.03 12. 1004900800047 1.250 2.37 12. 1004900800048 1.316 .960 12. 1004900800049 1.387 1.80 12. 1004900800050 1.463 1.60 12. 1004900800051 1.547 1.27 11. 1004900800052 1.637 1.68 11. 1004900800053 1.736 2.07 11. 1004900800054 1.834 1.19 10. 1004900800055 1.931 1.41 10. 1004900800056 2.036 1.36 10. 1004900800057 2.150 1.61 10. 1004900800058 2.274 1.59 10. 1004900800059 2.408 1.62 10. 1004900800060 2.555 1.31 10. 1004900800061 2.716 1.22 9. 1004900800062 2.873 1.02 9. 1004900800063 3.026 1.03 9. 1004900800064 3.190 1.41 8. 1004900800065 3.369 1.32 8. 1004900800066 3.563 .927 8. 1004900800067 3.774 .908 7. 1004900800068 4.004 .896 7. 1004900800069 4.256 .900 7. 1004900800070 4.533 .626 7. 1004900800071 4.838 .982 7. 1004900800072 5.130 .749 7. 1004900800073 5.402 .777 7. 1004900800074 5.697 .906 7. 1004900800075 6.016 .853 6. 1004900800076 6.363 .768 6. 1004900800077 6.741 .645 6. 1004900800078 7.154 .755 6. 1004900800079 7.606 .700 6. 1004900800080 8.102 .642 6. 1004900800081 8.648 .627 6. 1004900800082 9.251 .676 6. 1004900800083 9.920 .735 6. 1004900800084 10.66 .643 5. 1004900800085 11.35 .614 5. 1004900800086 11.95 .639 5. 1004900800087 12.59 .581 5. 1004900800088 13.29 .622 5. 1004900800089 14.05 .599 5. 1004900800090 14.88 .562 5. 1004900800091 15.78 .542 5. 1004900800092 16.76 .570 5. 1004900800093 17.85 .523 5. 1004900800094 19.03 .527 5. 1004900800095 20.35 .543 5. 1004900800096 21.80 .548 5. 1004900800097 23.42 .505 5. 1004900800098 25.22 .482 5. 1004900800099 27.23 .464 5. 1004900800100 29.50 .464 5. 1004900800101 32.07 .455 5. 1004900800102 34.98 .450 5. 1004900800103 38.31 .433 5. 1004900800104 42.14 .401 5. 1004900800105 45.39 .392 5. 1004900800106 47.77 .339 5. 1004900800107 50.36 .356 5. 1004900800108 53.15 .359 5. 1004900800109 56.19 .308 5. 1004900800110 59.49 .298 5. 1004900800111 63.10 .295 5. 1004900800112 67.04 .288 5. 1004900800113 71.37 .255 5. 1004900800114 76.12 .252 5. 1004900800115 81.37 .230 5. 1004900800116 87.18 .224 5. 1004900800117 93.64 .218 5. 1004900800118 100.8 .194 5. 1004900800119 108.9 .194 5. 1004900800120 118.0 .174 5. 1004900800121 128.2 .179 5. 1004900800122 139.9 .163 5. 1004900800123 153.2 .163 5. 1004900800124 168.5 .160 5. 1004900800125 186.2 .139 5. 1004900800126 206.9 .139 4. 1004900800127 231.2 .125 4. 1004900800128 260.1 .117 4. 1004900800129 294.7 .112 5. 1004900800130 336.8 .114 4. 1004900800131 388.5 .104 4. 1004900800132 453.2 .115 4. 1004900800133 535.4 .109 5. 1004900800134 642.3 .106 6. 1004900800135 752.0 .115 10. 1004900800136 ENDDATA 95 0 1004900800137 ENDSUBENT 136 0 1004900899999 NOSUBENT 10049009 19811120 00001004900900001 SUBENT 10049010 20120405 13811004901000001 BIB 7 16 1004901000002 REACTION 1(64-GD-155(N,EL),,WID,,2G) 1004901000003 2(64-GD-155(N,G),,WID) 1004901000004 SAMPLE (64-GD-155,ENR=0.9177) Enriched samples in oxide form. 1004901000005 Enrichment - Gd-155, 91.77%. 1004901000006 Natural gadolinium sample also used. 1004901000007 METHOD (TRN) Capture gammas, transmission and self-indication 1004901000008 measurements. 1004901000009 ANALYSIS (SHAPE,AREA) Shape and area analysis. 1004901000010 ERR-ANALYS (EN-RES-ERR) Uncertainties in resonance energy 1004901000011 determination taken to be one half of the 1004901000012 energy width of the time channel 1004901000013 (DATA-ERR) the standard deviation of the mean 1004901000014 calculated from the variance of the sample. 1004901000015 STATUS (TABLE) Data from Tbl. 3 of NP/A,146,337,1970 1004901000016 HISTORY (19720602C) 1004901000017 (19811118A) Subentries 9, 10 combined. 1004901000018 ENDBIB 16 0 1004901000019 NOCOMMON 0 0 1004901000020 DATA 6 90 1004901000021 EN-RES EN-RES-ERR DATA 1DATA-ERR 1DATA 2DATA-ERR 21004901000022 EV EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV 1004901000023 3.616 0.006 0.033 0.002 130. 17. 1004901000024 6.300 0.030 2.6 0.17 107.5 9.8 1004901000025 7.750 0.007 1.4 0.027 127. 4. 1004901000026 10.01 0.012 0.23 0.015 115. 20. 1004901000027 11.53 0.013 0.44 0.029 125. 23. 1004901000028 11.99 0.01 1.2 0.051 112. 11. 1004901000029 14.51 0.01 2.4 0.12 111. 10. 1004901000030 17.77 0.02 0.50 0.033 120. 25. 1004901000031 19.92 0.02 5.0 0.43 108. 16. 1004901000032 21.02 0.04 19. 1.2 101. 6. 1004901000033 23.65 0.04 3.9 0.099 167. 14. 1004901000034 27.57 0.05 0.84 0.023 1004901000035 29.58 0.06 5.4 0.42 90. 22. 1004901000036 30.10 0.06 12. 0.85 105. 11. 1004901000037 31.72 0.06 1.3 0.04 73. 57. 1004901000038 33.14 0.07 1.1 0.5 1004901000039 33.50 0.07 1.3 0.4 1004901000040 34.83 0.07 4.6 0.17 1004901000041 35.45 0.07 2.3 0.12 1004901000042 37.13 0.08 5.6 0.17 147. 18. 1004901000043 39.00 0.08 1.4 0.44 1004901000044 43.92 0.10 12. 0.4 136. 9. 1004901000045 46.10 0.10 2.6 0.18 1004901000046 46.82 0.10 6.5 0.2 84. 12. 1004901000047 47.70 0.11 0.49 0.036 1004901000048 51.36 0.07 14. 0.7 1004901000049 52.10 0.08 14. 0.52 1004901000050 53.01 0.08 1.8 0.06 1004901000051 53.68 0.08 9.6 0.45 72. 10. 1004901000052 56.17 0.08 2.7 0.11 61. 55. 1004901000053 59.32 0.09 8.1 0.22 1004901000054 62.74 0.09 9.8 0.4 82. 11. 1004901000055 64.00 0.10 0.36 0.017 1004901000056 65.15 0.10 0.84 0.042 1004901000057 69.50 0.10 7.9 0.29 151. 36. 1004901000058 76.90 0.12 2.1 0.076 1004901000059 77.70 0.12 0.97 0.053 1004901000060 78.80 0.12 5.7 0.46 47. 23. 1004901000061 80.05 0.12 0.39 0.14 1004901000062 80.80 0.12 1.9 0.2 1004901000063 84.05 0.13 6.9 0.23 1004901000064 84.95 0.13 2.3 0.12 1004901000065 90.50 0.13 1.6 0.062 1004901000066 92.50 0.15 2.7 0.29 1004901000067 93.00 0.15 3.9 0.36 1004901000068 94.10 0.15 0.68 0.045 1004901000069 95.86 0.15 4.8 0.33 1004901000070 96.55 0.15 4.5 0.31 1004901000071 98.33 0.16 13. 0.39 1004901000072 100.3 0.1 1.5 0.16 1004901000073 101.4 0.1 3.4 0.3 1004901000074 102.2 0.1 1.3 0.2 1004901000075 104.4 0.1 6.3 1.6 1004901000076 105.9 0.1 4.6 0.38 1004901000077 107.1 0.1 7.7 0.64 1004901000078 109.6 0.1 3.5 0.3 1004901000079 112.4 0.1 10. 2.4 84. 10. 1004901000080 113.8 0.2 25. 4.4 67. 12. 1004901000081 116.6 0.2 15. 2.6 116. 94. 1004901000082 118.7 0.2 2.5 0.2 1004901000083 123.4 0.2 27. 4.3 159. 65. 1004901000084 124.5 0.2 7.6 0.91 1004901000085 126.1 0.2 15. 2.1 152. 131. 1004901000086 128.6 0.2 1.4 0.17 1004901000087 129.8 0.2 3.2 0.53 1004901000088 130.9 0.2 35. 6.1 1004901000089 133.1 0.2 3.1 0.36 1004901000090 133.9 0.2 3.4 0.5 1004901000091 134.8 0.2 1.1 0.18 1004901000092 137.8 0.2 16. 1.5 1004901000093 140.4 0.2 3.1 0.34 1004901000094 141.4 0.2 1.3 0.21 1004901000095 145.7 0.2 7.7 0.7 1004901000096 146.9 0.2 5.3 0.58 1004901000097 148.2 0.2 12. 1.4 1004901000098 149.6 0.2 25. 7.2 1004901000099 150.2 0.2 31. 11. 1004901000100 152.2 0.2 6.2 0.54 1004901000101 154.0 0.2 1.4 0.2 1004901000102 156.3 0.2 10. 0.84 1004901000103 160.1 0.2 12. 1.3 1004901000104 161.6 0.2 25. 3.2 1004901000105 168.3 0.2 22. 2.4 1004901000106 170.3 0.2 10. 1.5 1004901000107 171.4 0.2 12. 1.8 1004901000108 173.6 0.2 38. 8. 110. 29. 1004901000109 175.5 0.2 2.6 0.29 1004901000110 178.0 0.2 8.0 0.69 1004901000111 180.4 0.3 11. 1.1 1004901000112 183.3 0.3 9. 0.8 1004901000113 ENDDATA 92 0 1004901000114 ENDSUBENT 113 0 1004901099999 NOSUBENT 10049011 19811120 00001004901100001 SUBENT 10049012 20120405 13811004901200001 BIB 7 16 1004901200002 REACTION 1(64-GD-157(N,EL),,WID,,2G) 1004901200003 2(64-GD-157(N,G),,WID) 1004901200004 SAMPLE (64-GD-157,ENR=0.8863) Enriched samples in oxide form. 1004901200005 Enrichment - Gd-157, 88.63%. 1004901200006 Natural gadolinium sample also used. 1004901200007 METHOD (TRN) Capture gammas, transmission and self indication 1004901200008 measurements. 1004901200009 ANALYSIS (SHAPE,AREA) Shape and area analysis. 1004901200010 ERR-ANALYS (EN-RES-ERR) Uncertainties in resonance energy 1004901200011 determination taken to be one half of the 1004901200012 energy width of the time channel 1004901200013 (DATA-ERR) the standard deviation of the mean 1004901200014 calculated from the variance of the sample. 1004901200015 STATUS (TABLE) Data from Tbl. 4 of NP/A,146,337,1970 1004901200016 HISTORY (19720602C) 1004901200017 (19811118A) subentries 11,12 combined. 1004901200018 ENDBIB 16 0 1004901200019 NOCOMMON 0 0 1004901200020 DATA 6 32 1004901200021 EN-RES EN-RES-ERR DATA 1DATA-ERR 1DATA 2DATA-ERR 21004901200022 EV EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV 1004901200023 16.25 0.2 0.3 0.1 1004901200024 16.85 0.11 18. 1.1 77. 5. 1004901200025 20.56 0.04 17. 1.3 88. 5. 1004901200026 21.66 0.03 0.45 0.06 147. 65. 1004901200027 23.33 0.02 0.59 0.05 121. 31. 1004901200028 25.40 2.3 0.088 79. 23. 1004901200029 40.15 0.09 0.94 0.036 1004901200030 44.20 0.1 12. 0.55 91. 8. 1004901200031 48.72 0.11 30. 1.8 87. 4. 1004901200032 58.31 0.08 37. 2.2 104. 5. 1004901200033 66.57 0.1 11. 0.72 67. 12. 1004901200034 81.39 0.12 15. 0.89 1004901200035 82.24 0.13 7.7 0.51 1004901200036 87.20 0.14 12. 0.79 113. 33. 1004901200037 96.59 0.15 14. 1.1 1004901200038 100.2 0.1 26. 5.8 103. 31. 1004901200039 104.9 0.1 38. 8.8 66. 9. 1004901200040 107.4 0.1 5.8 0.61 1004901200041 110.5 0.1 60. 13. 87. 10. 1004901200042 115.4 0.2 24. 5.7 113. 56. 1004901200043 120.9 0.09 198. 10. 91. 6. 1004901200044 138.2 0.2 60. 18. 1004901200045 139.3 0.2 5.3 1.4 1004901200046 143.7 0.2 72. 18. 88. 10. 1004901200047 148.4 0.2 14. 1.5 1004901200048 156.6 0.2 24. 8.6 87. 10. 1004901200049 164.9 0.2 30. 12. 1004901200050 168.3 0.2 2.5 0.39 1004901200051 169.5 0.2 4.2 0.61 1004901200052 171.4 0.2 29. 4.5 1004901200053 178.7 0.3 19. 2.1 1004901200054 184.0 0.3 21. 2.5 1004901200055 ENDDATA 34 0 1004901200056 ENDSUBENT 55 0 1004901299999 SUBENT 10049013 20120405 13811004901300001 BIB 4 9 1004901300002 REACTION 1(64-GD-155(N,G),,WID,,AV) 1004901300003 2(64-GD-155(N,EL),,WID/RED,,AV) 1004901300004 ERR-ANALYS (DATA-ERR) the standard deviation 1004901300005 STATUS (TABLE) Data from Tbl.5 of NP,147,337,1970 1004901300006 (DEP,10049010) Value derived from resolved parameters 1004901300007 HISTORY (19720602C) 1004901300008 (19811118A) subentries 13,14 combined. 1004901300009 (20120405A) SD: METHOD deleted. BIB updated. Values 1004901300010 for second REACTION corrected according to the Table. 1004901300011 ENDBIB 9 0 1004901300012 NOCOMMON 0 0 1004901300013 DATA 7 1 1004901300014 EN-RES-MIN EN-RES-MAX DATA 1DATA-ERR 1DATA 2DATA-ERR 21004901300015 MOMENTUM L2 1004901300016 EV EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV 1004901300017 NO-DIM 1004901300018 3.0 200.0 107.4 2.6 0.78 0.12 1004901300019 0. 1004901300020 ENDDATA 6 0 1004901300021 ENDSUBENT 20 0 1004901399999 NOSUBENT 10049014 19811120 00001004901400001 SUBENT 10049015 20120405 13811004901500001 BIB 4 6 1004901500002 REACTION (64-GD-155(N,0),,D) 1004901500003 ERR-ANALYS (DATA-ERR) the standard deviation 1004901500004 STATUS (TABLE) Data from Tbl.5 of NP,147,337,1970 1004901500005 (DEP,10049010) Value derived from resolved parameters 1004901500006 HISTORY (19720602C) 1004901500007 (20120405A) SD: METHOD deleted. BIB updated. 1004901500008 ENDBIB 6 0 1004901500009 NOCOMMON 0 0 1004901500010 DATA 5 1 1004901500011 EN-RES-MIN EN-RES-MAX DATA +DATA-ERR -DATA-ERR 1004901500012 EV EV EV EV EV 1004901500013 3.0 200.0 1.99 0.17 0.15 1004901500014 ENDDATA 3 0 1004901500015 ENDSUBENT 14 0 1004901599999 SUBENT 10049016 20120405 13811004901600001 BIB 5 10 1004901600002 REACTION (64-GD-155(N,EL),,STF) 1004901600003 ERR-ANALYS (DATA-ERR) the standard deviation 1004901600004 FLAG (1.) Value derived from average capture cross section. 1004901600005 (2.) Value derived from resolved parameters 1004901600006 STATUS (TABLE) Data from Tbl.5 of NP,147,337,1970 1004901600007 (DEP,10049023) Value derived from average capture 1004901600008 cross section. 1004901600009 (DEP,10049010) Value derived from resolved parameters 1004901600010 HISTORY (19720602C) 1004901600011 (20120405A) SD: METHOD deleted. BIB updated. 1004901600012 ENDBIB 10 0 1004901600013 COMMON 1 3 1004901600014 MOMENTUM L 1004901600015 NO-DIM 1004901600016 0.0 1004901600017 ENDCOMMON 3 0 1004901600018 DATA 6 2 1004901600019 EN-RES-MIN EN-RES-MAX DATA +DATA-ERR -DATA-ERR FLAG 1004901600020 EV EV NO-DIM NO-DIM NO-DIM NO-DIM 1004901600021 3.0 200.0 2.17E-04 0.30E-04 0.14E-04 2.1004901600022 1.0E+03 20.0E+03 2.55E-04 0.56E-04 0.46E-04 1.1004901600023 ENDDATA 4 0 1004901600024 ENDSUBENT 23 0 1004901699999 SUBENT 10049017 20120405 13811004901700001 BIB 4 7 1004901700002 REACTION (64-GD-155(N,EL),,STF) 1004901700003 ERR-ANALYS (DATA-ERR) the standard deviation 1004901700004 STATUS (TABLE) Data from Tbl.5 of NP,147,337,1970 1004901700005 (DEP,10049023) Value derived from average capture 1004901700006 cross section. 1004901700007 HISTORY (19720602C) 1004901700008 (20120405A) SD: METHOD, FLAG deleted. BIB update. 1004901700009 ENDBIB 7 0 1004901700010 COMMON 1 3 1004901700011 MOMENTUM L 1004901700012 NO-DIM 1004901700013 1.0 1004901700014 ENDCOMMON 3 0 1004901700015 DATA 5 1 1004901700016 EN-RES-MIN EN-RES-MAX DATA +DATA-ERR -DATA-ERR 1004901700017 EV EV NO-DIM NO-DIM NO-DIM 1004901700018 1.0E+03 2.0E+04 3.7E-04 1.4E-04 1.2E-04 1004901700019 ENDDATA 3 0 1004901700020 ENDSUBENT 19 0 1004901799999 SUBENT 10049018 20120405 13811004901800001 BIB 4 6 1004901800002 REACTION (64-GD-157(N,G),,WID,,AV) 1004901800003 ERR-ANALYS (DATA-ERR) the standard deviation 1004901800004 STATUS (TABLE) Data from Tbl.5 of NP,147,337,1970 1004901800005 (DEP,10049012) Value derived from resolved parameters 1004901800006 HISTORY (19720602C) 1004901800007 (20120405A) SD: METHOD deleted. BIB updated. 1004901800008 ENDBIB 6 0 1004901800009 NOCOMMON 0 0 1004901800010 DATA 4 1 1004901800011 EN-RES-MIN EN-RES-MAX DATA DATA-ERR 1004901800012 EV EV MILLI-EV MILLI-EV 1004901800013 3.0 200.0 102.6 2.0 1004901800014 ENDDATA 3 0 1004901800015 ENDSUBENT 14 0 1004901899999 SUBENT 10049019 20120405 13811004901900001 BIB 4 6 1004901900002 REACTION (64-GD-157(N,EL),,WID/RED,,AV) 1004901900003 ERR-ANALYS (DATA-ERR) the standard deviation 1004901900004 STATUS (TABLE) Data from Tbl.5 of NP,147,337,1970 1004901900005 (DEP,10049012) Value derived from resolved parameters 1004901900006 HISTORY (19720602C) 1004901900007 (20120405A) SD: METHOD deleted. BIB updated. 1004901900008 ENDBIB 6 0 1004901900009 NOCOMMON 0 0 1004901900010 DATA 6 1 1004901900011 EN-RES-MIN EN-RES-MAX DATA +DATA-ERR -DATA-ERR MOMENTUM L 1004901900012 EV EV MILLI-EV MILLI-EV MILLI-EV NO-DIM 1004901900013 3.0 200.0 2.53 0.72 0.52 0. 1004901900014 ENDDATA 3 0 1004901900015 ENDSUBENT 14 0 1004901999999 SUBENT 10049020 20120405 13811004902000001 BIB 4 6 1004902000002 REACTION (64-GD-157(N,0),,D) 1004902000003 ERR-ANALYS (DATA-ERR) the standard deviation 1004902000004 STATUS (TABLE) Data from Tbl.5 of NP,147,337,1970 1004902000005 (DEP,10049012) Value derived from resolved parameters 1004902000006 HISTORY (19720602C) 1004902000007 (20120405A) SD: METHOD deleted. BIB updated. 1004902000008 ENDBIB 6 0 1004902000009 NOCOMMON 0 0 1004902000010 DATA 5 1 1004902000011 EN-RES-MIN EN-RES-MAX DATA +DATA-ERR -DATA-ERR 1004902000012 EV EV EV EV EV 1004902000013 3.0 200.0 5.6 0.8 0.7 1004902000014 ENDDATA 3 0 1004902000015 ENDSUBENT 14 0 1004902099999 SUBENT 10049021 20120405 13811004902100001 BIB 5 10 1004902100002 REACTION (64-GD-157(N,EL),,STF) 1004902100003 ERR-ANALYS (DATA-ERR) the standard deviation 1004902100004 FLAG (1.) Value derived from average capture cross section. 1004902100005 (2.) Value derived from resolved parameters 1004902100006 STATUS (TABLE) Data from Tbl.5 of NP,147,337,1970 1004902100007 (DEP,10049024) Value derived from average capture 1004902100008 cross section. 1004902100009 (DEP,10049012) Value derived from resolved parameters 1004902100010 HISTORY (19720602C) 1004902100011 (20120405A) SD: METHOD, deleted. BIB update. 1004902100012 ENDBIB 10 0 1004902100013 COMMON 1 3 1004902100014 MOMENTUM L 1004902100015 NO-DIM 1004902100016 0.0 1004902100017 ENDCOMMON 3 0 1004902100018 DATA 6 2 1004902100019 EN-RES-MIN EN-RES-MAX DATA +DATA-ERR -DATA-ERR FLAG 1004902100020 EV EV NO-DIM NO-DIM NO-DIM NO-DIM 1004902100021 3.0 200.0 2.3E-04 0.9E-04 0.5E-04 2.1004902100022 1.0E+03 2.0E+04 2.3E-04 0.8E-04 0.8E-04 1.1004902100023 ENDDATA 4 0 1004902100024 ENDSUBENT 23 0 1004902199999 SUBENT 10049022 20120405 13811004902200001 BIB 4 7 1004902200002 REACTION (64-GD-157(N,EL),,STF) 1004902200003 ERR-ANALYS (DATA-ERR) the standard deviation 1004902200004 STATUS (TABLE) Data from Tbl.5 of NP,147,337,1970 1004902200005 (DEP,10049024) Value derived from average capture 1004902200006 cross section. 1004902200007 HISTORY (19720602C) 1004902200008 (20120405A) SD: METHOD,FLAG deleted. BIB update. 1004902200009 ENDBIB 7 0 1004902200010 COMMON 1 3 1004902200011 MOMENTUM L 1004902200012 NO-DIM 1004902200013 1.0 1004902200014 ENDCOMMON 3 0 1004902200015 DATA 5 1 1004902200016 EN-RES-MIN EN-RES-MAX DATA +DATA-ERR -DATA-ERR 1004902200017 EV EV NO-DIM NO-DIM NO-DIM 1004902200018 1.0E+03 2.0E+04 2.1E-04 1.4E-04 1.2E-04 1004902200019 ENDDATA 3 0 1004902200020 ENDSUBENT 19 0 1004902299999 SUBENT 10049023 20120405 13811004902300001 BIB 7 34 1004902300002 REACTION (64-GD-155(N,G)64-GD-156,,SIG) 1004902300003 SAMPLE (64-GD-155,ENR=0.9177) Enriched samples in oxide form. 1004902300004 METHOD (TOF) Time-of-flight. 230 m flight path. 1004902300005 MONITOR (5-B-10(N,A)3-LI-7,,SIG) Below 80 keV. 1004902300006 (1-H-1(N,EL)1-H-1,,SIG) Above 80 keV. 1004902300007 CORRECTION Corrected for detection efficiency, resonance self- 1004902300008 shielding, multiple scattering. 1004902300009 Correction for finite sample effects less than 15% 1004902300010 above 5 keV. 1004902300011 ERR-ANALYS (DATA-ERR) The overall uncertainty in the shape of the 1004902300012 cross sections is obtained from the following 1004902300013 energy-dependent components: 1004902300014 * statistical and systematic uncertainties in the 1004902300015 gamma-ray counts and neutron flux data (including 1004902300016 contributions from backgrounds); 1004902300017 * an estimated 20% uncertainty in the correction 1004902300018 applied at high energies for the effect of the 1004902300019 variation of the gamma-ray pulse-height distribution1004902300020 with neutron energy; 1004902300021 * and estimated uncertainties in the corrections 1004902300022 applied for multiple scattering and resonance 1004902300023 self-shielding. 1004902300024 (ERR-1) The major uncertainties in the normalization 1004902300025 of the capture cross sections are: 1004902300026 * the uncertainty (typically < 5%) in the absolute 1004902300027 capture probability determined from the areas of 1004902300028 resolved resonances; 1004902300029 * a 5% uncertainty from systematic errors in the flux 1004902300030 measurements; 1004902300031 * and an uncertainty (~ 5%) in the gamma-ray yield 1004902300032 at the matching region 2-8 keV due to a 20% 1004902300033 uncertainty in the determination of background 1004902300034 caused by neutrons scattered from the sample. 1004902300035 STATUS (TABLE) data from priv.com. in pdf-file. 1004902300036 ENDBIB 34 0 1004902300037 COMMON 1 3 1004902300038 ERR-1 1004902300039 PER-CENT 1004902300040 10. 1004902300041 ENDCOMMON 3 0 1004902300042 DATA 3 12 1004902300043 EN DATA DATA-ERR 1004902300044 KEV B PER-CENT 1004902300045 1.0 17.8 10. 1004902300046 1.5 15.7 1004902300047 2.0 13.0 1004902300048 3.0 9.65 1004902300049 4.0 9.01 1004902300050 6.0 6.74 1004902300051 8.0 5.43 1004902300052 10.0 4.98 1004902300053 13.0 4.38 1004902300054 15.0 3.91 1004902300055 18.0 3.63 1004902300056 22.5 3.37 10. 1004902300057 ENDDATA 14 0 1004902300058 ENDSUBENT 57 0 1004902399999 SUBENT 10049024 20120405 13811004902400001 BIB 7 34 1004902400002 REACTION (64-GD-157(N,G)64-GD-158,,SIG) 1004902400003 SAMPLE (64-GD-157,ENR=0.8863) Enriched samples in oxide form. 1004902400004 METHOD (TOF) Time-of-flight. 230 m flight path. 1004902400005 MONITOR (5-B-10(N,A)3-LI-7,,SIG) Below 80 keV. 1004902400006 (1-H-1(N,EL)1-H-1,,SIG) Above 80 keV. 1004902400007 CORRECTION Corrected for detection efficiency, resonance self- 1004902400008 shielding, multiple scattering. 1004902400009 Correction for finite sample effects less than 15% 1004902400010 above 5 keV. 1004902400011 ERR-ANALYS (DATA-ERR) The overall uncertainty in the shape of the 1004902400012 cross sections is obtained from the following 1004902400013 energy-dependent components: 1004902400014 * statistical and systematic uncertainties in the 1004902400015 gamma-ray counts and neutron flux data (including 1004902400016 contributions from backgrounds); 1004902400017 * an estimated 20% uncertainty in the correction 1004902400018 applied at high energies for the effect of the 1004902400019 variation of the gamma-ray pulse-height distribution1004902400020 with neutron energy; 1004902400021 * and estimated uncertainties in the corrections 1004902400022 applied for multiple scattering and resonance 1004902400023 self-shielding. 1004902400024 (ERR-1) The major uncertainties in the normalization 1004902400025 of the capture cross sections are: 1004902400026 * the uncertainty (typically < 5%) in the absolute 1004902400027 capture probability determined from the areas of 1004902400028 resolved resonances; 1004902400029 * a 5% uncertainty from systematic errors in the flux 1004902400030 measurements; 1004902400031 * and an uncertainty (~ 5%) in the gamma-ray yield 1004902400032 at the matching region 2-8 keV due to a 20% 1004902400033 uncertainty in the determination of background 1004902400034 caused by neutrons scattered from the sample. 1004902400035 STATUS (TABLE) data from priv.com. in pdf-file. 1004902400036 ENDBIB 34 0 1004902400037 COMMON 1 3 1004902400038 ERR-1 1004902400039 PER-CENT 1004902400040 10. 1004902400041 ENDCOMMON 3 0 1004902400042 DATA 3 12 1004902400043 EN DATA DATA-ERR 1004902400044 KEV B PER-CENT 1004902400045 1.0 10.3 10. 1004902400046 1.5 9.53 1004902400047 2.0 6.95 1004902400048 3.0 5.24 1004902400049 4.0 4.68 1004902400050 6.0 3.62 1004902400051 8.0 2.99 1004902400052 10.0 2.66 1004902400053 13.0 2.17 1004902400054 15.0 2.13 1004902400055 18.0 1.90 1004902400056 22.5 1.58 15. 1004902400057 ENDDATA 14 0 1004902400058 ENDSUBENT 57 0 1004902499999 ENDENTRY 24 0 1004999999999