ENTRY 13828 20020409 00001382800000001 SUBENT 13828001 20020409 00001382800100001 BIB 11 20 1382800100002 INSTITUTE (1USAANL) 1382800100003 REFERENCE (J,PR/C,14,75,197607) 1382800100004 AUTHOR (D.L.Bushnell,G.R.Tassotto,R.K.Smither) 1382800100005 TITLE States excited in 146Nd by thermal and average- 1382800100006 resonance neutron-capture gamma rays. 1382800100007 FACILITY (REAC,1USAANL) Internal target facility at Argonne 1382800100008 CP-5 research reactor. 1382800100009 INC-SOURCE (REAC) Reactor core with a thermal-neutron flux ~3E+13 1382800100010 n/(cm2.s). 1382800100011 DETECTOR (GE-IN) A 4-cm3 cooled intrinsic-germanium detector 1382800100012 located in a Compton-suppression pair spectrometer, 1382800100013 used in both coincidence and anticoincidence modes. 1382800100014 MONITOR Energy and intensity calibrations based primarily on 1382800100015 the known lines from the 14N(n,g)15N reaction. 1382800100016 Calibration spectrum collected with target in place 1382800100017 and nitrogen gas used to flush the through tube. 1382800100018 ADD-RES Capture state (neutron separation) energy of 146Nd 1382800100019 determined to be 7564.7(2) keV. 1382800100020 STATUS Data taken from Table III, IV, and V in reference. 1382800100021 HISTORY (20020327C) IS 1382800100022 ENDBIB 20 0 1382800100023 NOCOMMON 0 0 1382800100024 ENDSUBENT 23 0 1382800199999 SUBENT 13828002 20020409 00001382800200001 BIB 7 18 1382800200002 REACTION (60-ND-145(N,G)60-ND-146,,SPC,,REL/SPA) 1382800200003 INC-SPECT Reactor spectrum 1382800200004 SAMPLE Three targets used. 1382800200005 . Two neodymium oxide targets, about 50 mg, contained 1382800200006 in small graphite holders. One target enriched to 1382800200007 89.67% in 145Nd, the other enriched to 91.06% in 1382800200008 143Nd (0.39% 145Nd). 1382800200009 . Natural neodymium target (8.3% 145Nd), about 25 g. 1382800200010 METHOD (COINC) The spectrometer used in the coincidence mode 1382800200011 which allowed only double escape events to be 1382800200012 recorded. 1382800200013 ANALYSIS Isotopic identifications made by comparison of thermal-1382800200014 neutron-capture gamma-ray spectra from the target 1382800200015 enriched in 143Nd, from the target enriched in 145Nd, 1382800200016 and from the natural target. 1382800200017 ERR-ANALYS (DATA-ERR) Intensity uncertainties. 1382800200018 REL-REF (R,,J.K.HAWKINS,T,HAWKINS,1974) Data primarily taken 1382800200019 from this experiment. 1382800200020 ENDBIB 18 0 1382800200021 COMMON 1 3 1382800200022 EN-DUMMY 1382800200023 EV 1382800200024 0.0253 1382800200025 ENDCOMMON 3 0 1382800200026 DATA 4 41 1382800200027 E E-ERR DATA DATA-ERR 1382800200028 KEV KEV ARB-UNITS PER-CENT 1382800200029 7110.8 0.3 390. 1.5 1382800200030 6521.3 0.4 206. 2.0 1382800200031 6375.0 0.3 17.0 8.0 1382800200032 6093.9 0.3 314. 2.2 1382800200033 5818.3 0.3 5.2 17. 1382800200034 5787.4 0.2 100. 2.2 1382800200035 5777.4 0.2 11.7 9.0 1382800200036 5752.5 0.5 4.2 20. 1382800200037 5645.7 0.2 45.1 3.6 1382800200038 5587.5 0.2 13.7 15. 1382800200039 5575.3 0.3 24.5 3.8 1382800200040 5492.3 0.4 3.6 19. 1382800200041 5468.7 0.3 10.2 7.4 1382800200042 5367.3 0.3 15.6 5.5 1382800200043 5344.8 0.3 11.6 7.5 1382800200044 5338.2 0.3 5.5 16. 1382800200045 5207.6 0.2 47.8 2.7 1382800200046 5131.0 0.5 3.1 26. 1382800200047 5128.2 0.3 7.5 9.9 1382800200048 5125.8 0.3 3.4 20. 1382800200049 5094.7 0.3 10.3 7.7 1382800200050 5073.2 0.3 11.5 6.7 1382800200051 5048.3 0.3 24.7 4.2 1382800200052 5043.3 0.3 39.6 3.2 1382800200053 5036.3 0.3 6.7 12. 1382800200054 5011.9 0.2 76.4 2.1 1382800200055 5002.5 0.3 14.0 6.4 1382800200056 4990.9 0.3 5.4 14. 1382800200057 4975.1 0.3 29.4 3.7 1382800200058 4903.8 0.3 5.2 15. 1382800200059 4857.3 0.3 4.3 18. 1382800200060 4814.5 0.2 26.7 4.2 1382800200061 4780.8 0.3 10.1 8.5 1382800200062 4720.0 0.3 4.2 19. 1382800200063 4694.0 0.3 2.2 35. 1382800200064 4679.3 0.3 5.2 20. 1382800200065 4634.0 0.2 22.7 5.0 1382800200066 4595.0 0.3 6.4 15. 1382800200067 4567.9 0.2 46.9 3.0 1382800200068 4551.4 0.5 5.6 30. 1382800200069 4473.4 0.3 5.7 15. 1382800200070 ENDDATA 43 0 1382800200071 ENDSUBENT 70 0 1382800299999 SUBENT 13828003 20020409 00001382800300001 BIB 8 22 1382800300002 REACTION (60-ND-145(N,G)60-ND-146,,SPC,,REL/SPA) 1382800300003 INC-SPECT Reactor spectrum effectively limited by boron that 1382800300004 removes low-energy neutrons. Dominant contributions to1382800300005 spectrum were from neutrons in the approximate energy 1382800300006 range 200-500 eV. 1382800300007 SAMPLE Natural neodymium target (8.3% 145Nd), about 25 g, 1382800300008 surrounded by 0.95-cm thick boron absorber. 1382800300009 METHOD (COINC) Average-resonance neutron-capture gamma-ray 1382800300010 experiment. Spectra obtained with the spectrometer 1382800300011 system in the coincidence mode which allowed only 1382800300012 double escape events to be recorded. 1382800300013 ANALYSIS Capture averaged over many neutron resonances in order 1382800300014 to average out Porter-Thomas fluctuations in the 1382800300015 intensities of primary transitions resulting from 1382800300016 capture in a single resonance. 1382800300017 ERR-ANALYS (DATA-ERR) Intensity uncertainties. 1382800300018 FLAG (1.) Reduced relative intensities, i.e., measured 1382800300019 intensities multiplied by a factor (E0/E)**3, where 1382800300020 E0=7564.7 keV is the capture state energy and E is the1382800300021 gamma-ray energy. 1382800300022 REL-REF (N,,L.M.Bollinger+,J,PR/C,2,1951,1970) 1382800300023 Average-resonance neutron-capture technique. 1382800300024 ENDBIB 22 0 1382800300025 COMMON 2 3 1382800300026 EN-MIN EN-MAX 1382800300027 EV EV 1382800300028 200. 500. 1382800300029 ENDCOMMON 3 0 1382800300030 DATA 5 55 1382800300031 E E-ERR DATA DATA-ERR FLAG 1382800300032 KEV KEV ARB-UNITS PER-CENT NO-DIM 1382800300033 7110.8 0.3 5.5 12. 1. 1382800300034 6521.3 0.4 17.6 6. 1. 1382800300035 6375.0 0.3 1.6 29. 1. 1382800300036 6093.9 0.3 5.7 11. 1. 1382800300037 5818.3 0.3 10.7 7. 1. 1382800300038 5787.4 0.2 10.0 7. 1. 1382800300039 5777.4 0.2 4.7 14. 1. 1382800300040 5752.5 0.5 0.81 80. 1. 1382800300041 5680.0 0.5 0.86 83. 1. 1382800300042 5669.1 1.0 0.43 100. 1. 1382800300043 5645.7 0.2 5.3 12. 1. 1382800300044 5587.5 0.2 3.4 20. 1. 1382800300045 5575.3 0.3 5.6 13. 1. 1382800300046 5492.3 0.4 1.4 85. 1. 1382800300047 5468.7 0.3 6.2 13. 1. 1382800300048 5367.3 0.3 9.5 10. 1. 1382800300049 5344.8 0.5 5.0 17. 1. 1382800300050 5338.2 0.5 4.2 22. 1. 1382800300051 5333.7 0.7 1.8 50. 1. 1382800300052 5277.6 0.6 5.1 18. 1. 1382800300053 5262.6 0.5 4.7 21. 1. 1382800300054 5207.6 0.2 5.8 17. 1. 1382800300055 5145.3 0.3 4.9 22. 1. 1382800300056 5131.0 0.5 1.7 61. 1. 1382800300057 5128.2 0.5 4.5 25. 1. 1382800300058 5125.8 0.5 4.3 26. 1. 1382800300059 5094.7 0.3 6.0 19. 1. 1382800300060 5079.3 0.5 5.8 20. 1. 1382800300061 5073.2 0.5 6.5 18. 1. 1382800300062 5048.3 0.3 0.9 62. 1. 1382800300063 5043.3 0.4 4.5 26. 1. 1382800300064 5036.3 0.3 5.3 22. 1. 1382800300065 5016.9 0.4 5.7 20. 1. 1382800300066 5011.9 0.2 6.7 15. 1. 1382800300067 5008.7 0.3 9.2 10. 1. 1382800300068 5002.5 0.5 5.3 20. 1. 1382800300069 4990.9 0.3 10.3 8. 1. 1382800300070 4975.1 0.3 12.0 20. 1. 1382800300071 4963.1 0.6 1.5 76. 1. 1382800300072 4903.8 0.3 10.0 10. 1. 1382800300073 4857.5 0.5 7.0 20. 1. 1382800300074 4814.5 0.5 5.2 25. 1. 1382800300075 4780.8 0.4 8.2 15. 1. 1382800300076 4761.6 0.5 10.6 15. 1. 1382800300077 4658.9 0.6 6.2 25. 1. 1382800300078 4634.0 0.5 6.0 20. 1. 1382800300079 4606.1 0.5 5.5 25. 1. 1382800300080 4567.9 0.5 7.1 21. 1. 1382800300081 4551.4 0.4 8.2 18. 1. 1382800300082 4530.0 0.5 5.0 30. 1. 1382800300083 4522.4 0.5 6.7 23. 1. 1382800300084 4500.0 0.5 6.7 23. 1. 1382800300085 4392.6 0.5 7.2 22. 1. 1382800300086 4386.4 0.5 5.8 25. 1. 1382800300087 4334.9 0.4 8.0 20. 1. 1382800300088 ENDDATA 57 0 1382800300089 ENDSUBENT 88 0 1382800399999 SUBENT 13828004 20020409 00001382800400001 BIB 5 20 1382800400002 REACTION (60-ND-145(N,G)60-ND-146,,SPC,,REL/SPA) 1382800400003 INC-SPECT Reactor spectrum 1382800400004 SAMPLE Three targets used. 1382800400005 . Two neodymium oxide targets, about 50 mg, contained 1382800400006 in small graphite holders. One target enriched to 1382800400007 89.67% in 145Nd, the other enriched to 91.06% in 1382800400008 143Nd (0.39% 145Nd). 1382800400009 . Natural neodymium target (8.3% 145Nd), about 25 g. 1382800400010 ANALYSIS Investigated secondary gamma transitions in the energy 1382800400011 range from 400 to 2600 keV by rejection of all but 1382800400012 full-energy detector events (anticoincidence mode). 1382800400013 Isotopic identifications made by comparison of thermal-1382800400014 neutron-capture gamma-ray spectra from the target 1382800400015 enriched in 143Nd, from the target enriched in 145Nd, 1382800400016 and from the natural target. 1382800400017 ERR-ANALYS (DATA-ERR) Intensity uncertainties. 1382800400018 Contributions to relative intensity error due to errors1382800400019 in the linewidth, efficiency, and transmission were at1382800400020 most 2%, 10%, and 15%, respectively, up to 1500 keV. 1382800400021 Above 1500 keV the efficiency error was at most 20%. 1382800400022 ENDBIB 20 0 1382800400023 COMMON 1 3 1382800400024 EN-DUMMY 1382800400025 EV 1382800400026 0.0253 1382800400027 ENDCOMMON 3 0 1382800400028 DATA 4 155 1382800400029 E E-ERR DATA DATA-ERR 1382800400030 KEV KEV ARB-UNITS PER-CENT 1382800400031 448.4 0.6 1.1 18. 1382800400032 453.7 0.1 100.0 0.2 1382800400033 467.4 0.7 0.16 83. 1382800400034 471.4 0.6 0.70 30. 1382800400035 474.5 0.2 7.5 1.9 1382800400036 476.7 0.5 0.62 25. 1382800400037 479.2 0.5 0.83 20. 1382800400038 482.0 0.5 0.74 20. 1382800400039 522.9 0.6 0.30 25. 1382800400040 528.3 0.4 0.56 14. 1382800400041 534.9 0.6 0.25 30. 1382800400042 545.4 0.6 0.20 36. 1382800400043 555.9 0.2 2.4 2.9 1382800400044 565.1 0.6 0.25 25. 1382800400045 578.0 0.5 0.29 19. 1382800400046 584.6 0.6 0.32 17. 1382800400047 589.4 0.2 27.0 0.4 1382800400048 598.3 0.5 0.34 16. 1382800400049 600.0 0.8 0.12 50. 1382800400050 602.0 0.8 0.12 50. 1382800400051 630.1 0.5 0.17 29. 1382800400052 650.6 0.5 0.29 18. 1382800400053 674.3 0.4 0.10 50. 1382800400054 677.1 0.5 0.10 50. 1382800400055 702.1 0.2 1.7 3. 1382800400056 716.8 0.5 0.17 29. 1382800400057 721.6 0.5 0.07 63. 1382800400058 724.6 0.4 0.22 22. 1382800400059 729.6 0.5 0.25 20. 1382800400060 735.9 0.2 15.3 0.5 1382800400061 745.2 0.4 0.16 30. 1382800400062 757.7 0.5 0.15 32. 1382800400063 765.1 0.5 0.12 37. 1382800400064 772.5 0.2 0.39 12. 1382800400065 775.6 0.5 0.37 12. 1382800400066 788.8 0.3 0.43 11. 1382800400067 807.3 0.2 0.70 6.9 1382800400068 849.9 0.3 0.31 15. 1382800400069 868.5 0.4 0.26 18. 1382800400070 871.5 0.4 0.34 14. 1382800400071 875.9 0.2 1.7 2.9 1382800400072 883.3 0.2 1.1 5. 1382800400073 906.7 0.2 0.65 7. 1382800400074 923.2 0.2 1.1 5. 1382800400075 946.3 0.2 1.5 4. 1382800400076 1002.7 0.2 0.84 6. 1382800400077 1012.3 0.4 0.22 21. 1382800400078 1016.9 0.2 4.7 1.3 1382800400079 1029.6 0.3 0.17 28. 1382800400080 1036.8 0.3 0.25 19. 1382800400081 1039.5 0.3 0.16 30. 1382800400082 1053.1 0.2 0.78 6. 1382800400083 1081.1 0.2 0.34 13. 1382800400084 1093.5 0.3 0.14 32. 1382800400085 1125.1 0.2 1.0 5. 1382800400086 1139.9 0.2 0.48 10. 1382800400087 1149.8 0.4 0.21 22. 1382800400088 1165.2 0.5 0.12 38. 1382800400089 1167.2 0.2 0.64 7. 1382800400090 1169.5 0.4 0.30 15. 1382800400091 1181.7 0.4 0.15 31. 1382800400092 1183.6 0.4 0.24 19. 1382800400093 1190.8 0.4 0.30 15. 1382800400094 1193.4 0.4 0.31 19. 1382800400095 1219.9 0.4 0.22 21. 1382800400096 1244.0 0.4 0.22 20. 1382800400097 1268.5 0.4 0.22 20. 1382800400098 1292.2 0.3 0.64 7. 1382800400099 1314.3 0.3 0.79 7. 1382800400100 1324.0 0.3 3.4 1.7 1382800400101 1332.3 0.4 0.26 18. 1382800400102 1333.9 0.3 1.5 4. 1382800400103 1363.5 0.3 0.79 6. 1382800400104 1377.3 0.3 1.6 3. 1382800400105 1382.0 0.5 0.1 45. 1382800400106 1392.3 0.3 0.27 17. 1382800400107 1426.5 0.3 0.41 11. 1382800400108 1434.3 0.3 0.79 6. 1382800400109 1448.6 0.4 0.24 19. 1382800400110 1452.2 0.3 1.4 4. 1382800400111 1465.4 0.3 1.8 3. 1382800400112 1468.8 0.3 0.30 17. 1382800400113 1471.0 0.3 4.4 1.3 1382800400114 1478.6 0.3 0.45 10. 1382800400115 1496.5 0.4 0.11 40. 1382800400116 1502.9 0.4 0.22 20. 1382800400117 1521.9 0.3 1.3 4. 1382800400118 1525.5 0.5 0.90 5. 1382800400119 1536.0 0.3 0.66 7. 1382800400120 1560.1 0.3 0.29 15. 1382800400121 1579.5 0.4 0.34 13. 1382800400122 1613.9 0.3 0.49 9. 1382800400123 1637.8 0.6 0.23 19. 1382800400124 1665.6 0.3 0.33 13. 1382800400125 1671.8 0.4 0.19 23. 1382800400126 1680.9 0.4 0.31 14. 1382800400127 1689.8 0.4 0.31 14. 1382800400128 1728.4 0.5 0.20 22. 1382800400129 1741.4 0.3 0.48 10. 1382800400130 1744.3 0.3 1.0 5. 1382800400131 1750.7 0.3 0.32 14. 1382800400132 1766.7 0.2 1.0 5. 1382800400133 1771.1 0.3 0.16 26. 1382800400134 1777.3 0.3 0.12 35. 1382800400135 1779.8 0.3 0.12 35. 1382800400136 1787.3 0.3 0.17 23. 1382800400137 1812.1 0.3 0.29 15. 1382800400138 1832.9 0.3 0.25 17. 1382800400139 1853.3 0.3 0.25 17. 1382800400140 1862.7 0.3 0.34 13. 1382800400141 1873.5 0.4 0.24 18. 1382800400142 1880.5 0.5 0.21 15. 1382800400143 1903.2 0.4 0.31 15. 1382800400144 1906.8 0.6 0.09 50. 1382800400145 1910.8 0.6 0.09 50. 1382800400146 1914.1 0.6 0.10 45. 1382800400147 1917.4 1.0 0.06 80. 1382800400148 1919.7 1.0 0.07 80. 1382800400149 1944.2 0.3 0.15 30. 1382800400150 1969.0 0.5 0.16 40. 1382800400151 1975.1 0.5 0.11 60. 1382800400152 1977.7 0.5 0.23 50. 1382800400153 1981.4 0.3 0.42 20. 1382800400154 1984.2 0.4 0.43 20. 1382800400155 1989.2 0.5 0.18 60. 1382800400156 2003.0 0.3 0.16 30. 1382800400157 2030.0 0.3 0.18 25. 1382800400158 2037.8 0.3 0.46 10. 1382800400159 2045.6 0.3 0.17 25. 1382800400160 2057.8 0.3 0.18 25. 1382800400161 2083.2 0.3 0.20 20. 1382800400162 2096.3 1.0 0.10 50. 1382800400163 2108.3 0.2 0.46 9. 1382800400164 2120.2 0.3 0.38 11. 1382800400165 2136.0 0.2 0.71 6. 1382800400166 2142.5 0.5 0.10 43. 1382800400167 2149.1 0.3 0.31 13. 1382800400168 2157.6 1.0 0.07 60. 1382800400169 2168.5 0.3 0.13 33. 1382800400170 2207.0 0.3 0.23 19. 1382800400171 2209.4 0.3 0.23 19. 1382800400172 2223.5 0.2 1.3 4. 1382800400173 2234.5 0.3 0.21 20. 1382800400174 2266.8 0.3 0.17 24. 1382800400175 2278.1 0.3 0.10 40. 1382800400176 2291.2 0.3 0.13 31. 1382800400177 2369.5 0.3 0.12 33. 1382800400178 2459.8 0.3 0.14 30. 1382800400179 2658.9 0.4 0.20 20. 1382800400180 2685.6 0.3 0.15 31. 1382800400181 2691.3 0.3 0.13 33. 1382800400182 2793.0 0.4 0.14 29. 1382800400183 2830.3 0.5 0.24 18. 1382800400184 2852.8 0.4 0.12 36. 1382800400185 2856.5 0.4 0.23 19. 1382800400186 ENDDATA 157 0 1382800400187 ENDSUBENT 186 0 1382800499999 ENDENTRY 4 0 1382899999999