ENTRY 12857 20120710 13841285700000001 SUBENT 12857001 20120710 13841285700100001 BIB 15 66 1285700100002 INSTITUTE (1USAORL) 1285700100003 REFERENCE (J,PR/C,29,1996,198406) 1285700100004 AUTHOR (R.L.Macklin) 1285700100005 TITLE Resonance neutron capture by 35,37Cl. 1285700100006 FACILITY (LINAC,1USAORL) ORNL-ORELA facility 1285700100007 INC-SOURCE (PHOTO) 1285700100008 4-ns burst width for the natural sample(75.77% Cl-35) 1285700100009 5-ns burst width for the enriched Cl-37 sample. 1285700100010 Time-of-flight energy scale is calibrated with sharp 1285700100011 aluminum resonances at 5.903 keV and 1094 keV and 1285700100012 corrected for relativistic effects. 1285700100013 SAMPLE Enriched Cl-37 and natural samples. 1285700100014 METHOD (TOF) Time-of-flight-- 40m flight path. 1285700100015 DETECTOR (SCIN) Capture gamma-rays were detected by a 1285700100016 pair of non-hydrogenous liquid scintillators. 1285700100017 (GLASD) Thin 6Li glass scintillator used as a neutron 1285700100018 flux monitor 1285700100019 Detector efficiency was determined by the saturated 1285700100020 resonance method relative to the flux monitor. 1285700100021 ANALYSIS Breit-Wigner resonance fits were made to fit the 1285700100022 capture peaks with the help of LSFIT least-squares 1285700100023 code. Ref: Nucl.Sci.Eng., 59, 12,1976. 1285700100024 Experimental resolution function was simulated with 1285700100025 the convolution of Gaussian and exponential shapes. 1285700100026 When both g*Gn and Ggamma could be determined. 1285700100027 their correlation coefficient is given in the paper. 1285700100028 REL-REF (M,,R.L.Macklin,J,NSE,59,12,1976) - LSFIT 1285700100029 least-squares code description 1285700100030 (I,10999001,R.L.Macklin+,J,NSE,84,98,1983) - Figures of1285700100031 experimental arrangement for the ORELA neutron 1285700100032 capture facility 1285700100033 (M,12755001,H.Beer+,J,PR/C,26,1404,1982) - Description 1285700100034 of systematic uncertainty analysis. 1285700100035 (M,,R.L.Macklin+,J,NIM,164,213,1979) - Description of 1285700100036 saturated resonance method 1285700100037 (M,,R.L.Macklin+,J,NIM,96,509,1971) - Description of 1285700100038 neutron flux monitor 1285700100039 CORRECTION Boron filter was used to absorb neutrons from 1285700100040 earlier pulses. 1285700100041 Data were corrected for: 1285700100042 electronic dead time 1285700100043 beam-dependent backgrounds 1285700100044 gamma-ray energy loss in sample 1285700100045 linear subtraction matrix was used to remove the 1285700100046 minor isotope in each sample. 1285700100047 ERR-ANALYS (ERR-S) Statistical uncertainties. 1285700100048 (ERR-1) Cross section normalization uncertainty = 2.4% 1285700100049 (ERR-2,0.1,2.8) Flux uncertainty increasing with 1285700100050 energy = 0.1 to 2.8%. 1285700100051 * Neutron energy uncertainty is estimated to be 1285700100052 = 1/2 the resolution width or En/1300. 1285700100053 An estimated uncertainty for the scattered neutron 1285700100054 sensitivity was combined with tabulated statistical 1285700100055 uncertainty for the broadest capture resonance 1285700100056 parameters. Proximity of the 25.5 keV resonance 1285700100057 to the 27 keV fluorine resonance due to the C-6 F-6 1285700100058 material was high-about 25%. 1285700100059 STATUS (TABLE) Data taken from the pre-print of the article 1285700100060 submitted to Physical Review C (Jan 13,1984) (the same 1285700100061 data are published in Table 1,2 in the PR/C,29,1996). 1285700100062 (APRVD) R.L.Macklin, 1984/4/3. 1285700100063 HISTORY (19840215C) 1285700100064 (19840622A) Reference update. 1285700100065 (20120710A) SD:Updated to new date formats,lower case. 1285700100066 Corrected according to last EXFOR rules and Dict. 1285700100067 SF6 in REACTION code 2 was corrected in Subents 2,3.1285700100068 ENDBIB 66 0 1285700100069 COMMON 1 3 1285700100070 ERR-1 1285700100071 PER-CENT 1285700100072 2.4 1285700100073 ENDCOMMON 3 0 1285700100074 ENDSUBENT 73 0 1285700199999 SUBENT 12857002 20120710 13841285700200001 BIB 7 22 1285700200002 REACTION 1(17-CL-35(N,0),,EN) 1285700200003 2(17-CL-35(N,G),,WID/STR) 1285700200004 3(17-CL-35(N,EL),,WID,,G) 1285700200005 4(17-CL-35(N,G),,WID) 1285700200006 5(17-CL-35(N,0),,J) 1285700200007 SAMPLE (17-CL-35,NAT=0.7577) A slab of natural lithium 1285700200008 chloride, 26.2 mm x 51.6 mm x 3.91 mm and 1285700200009 weighing 7.400 g 1285700200010 ASSUMED (ASSUM1,17-CL-35(N,EL),,WID,,G) g*neutron width 1285700200011 adopted from refs. (see REL-REF) 1285700200012 (ASSUM2,17-CL-35(N,0),,J) J adopted (see REL-REF) 1285700200013 REL-REF (R,10518002,U.N.Singh+,J,PR/C,10,2138,1974) 1285700200014 (R,,R.N.Alvez+,J,NP/A,143,118,1969) 1285700200015 MISC-COL (MISC) Correlation coefficient between neutron width 1285700200016 and capture width 1285700200017 FLAG (1.) The 134.0,143.2 and 150.0 keV resonances are 1285700200018 probable doublets or multiplets. 1285700200019 (2.) The 182.5 keV resonance g*neutron width is equal 1285700200020 to the corresponding value obtained by Singh et al 1285700200021 minus the fitted value for the 183.6 keV resonance. 1285700200022 HISTORY (20120710A) SD: SF6=ARE was changed to WID/STR in 1285700200023 REACTION code 2. Subents 4,5. 1285700200024 ENDBIB 22 0 1285700200025 NOCOMMON 0 0 1285700200026 DATA 13 54 1285700200027 DATA 1DATA 2ERR-S 2DATA 3ERR-S 3DATA 41285700200028 ERR-S 4DATA 5MISC ASSUM1 STAT-W G ASSUM2 1285700200029 FLAG 1285700200030 KEV MILLI-EV MILLI-EV EV EV MILLI-EV 1285700200031 MILLI-EV NO-DIM NO-DIM EV NO-DIM NO-DIM 1285700200032 NO-DIM 1285700200033 4.252 99.0 0.4 437. 1285700200034 3. 1. 0.0 0.25 1285700200035 1285700200036 5.492 1.9 0.1 1285700200037 1285700200038 1285700200039 14.803 253.5 3.3 19.2 0.4 410. 1285700200040 5. 0.13 2.0 1285700200041 1285700200042 16.359 365.5 4.4 4.9 0.1 632. 1285700200043 9. -0.66 0.625 1285700200044 1285700200045 17.137 830.8 5.6 9.4 0.1 1458. 1285700200046 11. -0.52 1285700200047 1285700200048 22.40 89.1 1.9 0.10 0.03 1000. 1285700200049 0.625 1285700200050 1285700200051 26.61 237. 9. 79.7 3.3 380. 1285700200052 14. 0.28 0.625 1285700200053 1285700200054 27.35 268. 9. 28.4 0.1 475. 1285700200055 19. -0.88 0.625 1285700200056 1285700200057 37.78 53. 3. 1285700200058 1285700200059 1285700200060 40.28 118. 5. 1285700200061 1285700200062 1285700200063 44.19 450. 12. 9.7 0.4 1259. 1285700200064 36. 1. -0.62 1285700200065 1285700200066 51.63 63. 5. 105. 1285700200067 9. 1.6 0.625 1285700200068 1285700200069 53.00 207. 8. 1285700200070 1285700200071 1285700200072 54.96 168. 11. 22.9 2.3 452. 1285700200073 29. 1. -0.34 1285700200074 1285700200075 57.84 398. 15. 54.5 3.3 642. 1285700200076 24. 2. -0.17 1285700200077 1285700200078 62.80 260. 13. 46.0 3.9 697. 1285700200079 36. 1. 0.06 1285700200080 1285700200081 68.29 195. 14. 87.6 9.9 522. 1285700200082 36. 1. 0.29 1285700200083 1285700200084 75.51 65. 7. 1285700200085 1285700200086 1285700200087 90.50 655. 20. 1285700200088 1285700200089 1285700200090 95.28 149. 11. 1285700200091 1285700200092 1285700200093 96.67 162. 10. 1285700200094 1285700200095 1285700200096 99.48 238. 14. 1285700200097 1285700200098 1285700200099 103.53 220. 22. 159. 26. 587. 1285700200100 65. 1. 0.42 1285700200101 1285700200102 112.12 164. 16. 1285700200103 1285700200104 1285700200105 113.53 543. 33. 245. 25. 872. 1285700200106 52. 2. 0.29 1285700200107 1285700200108 115.15 289. 20. 1285700200109 1285700200110 1285700200111 130.6 271. 24. 1285700200112 1285700200113 1285700200114 134.0 1453. 93. 1285700200115 1285700200116 1. 1285700200117 135.0 106. 36. 283. 1285700200118 97. 1. 66. 1285700200119 1285700200120 140.2 485. 38. 1285700200121 1285700200122 1285700200123 140.9 413. 36. 665. 1285700200124 59. 2. 59. 1285700200125 1285700200126 141.7 353. 32. 1285700200127 1285700200128 1285700200129 143.2 412. 40. 1285700200130 1285700200131 1. 1285700200132 150.0 804. 58. 66. 7. 1285700200133 1. 1285700200134 1. 1285700200135 153.0 159. 27. 1285700200136 1285700200137 1285700200138 162.7 262. 34. 1285700200139 1285700200140 1285700200141 165.6 601. 61. 106. 18. 1612. 1285700200142 165. 1. -0.18 1285700200143 1285700200144 180.9 67. 31. 1285700200145 1285700200146 1285700200147 182.5 328. 135. 524. 1285700200148 217. 583. 0.625 1285700200149 2. 1285700200150 183.6 821. 139. 607. 160. 1316. 1285700200151 222. 0.70 0.625 1285700200152 1285700200153 185.4 417. 49. 1285700200154 1285700200155 1285700200156 188.3 947. 93. 375. 60. 1520. 1285700200157 150. 0.27 0.625 1285700200158 1285700200159 189.3 88. 36. 1285700200160 1285700200161 1285700200162 190.4 234. 41. 1285700200163 1285700200164 1285700200165 193.1 1130. 80. 116. 14. 1825. 1285700200166 132. -0.46 0.625 1285700200167 1285700200168 199.2 413. 51. 1285700200169 1285700200170 1285700200171 201.3 303. 77. 64. 24. 487. 1285700200172 125. -0.75 0.625 1285700200173 1285700200174 206.5 329. 41. 1285700200175 1285700200176 1285700200177 215.3 1268. 171. 384. 65. 2036. 1285700200178 274. 0.60 0.625 1285700200179 1285700200180 216.0 522. 554. 3000. 1285700200181 0.625 1285700200182 1285700200183 217.3 697. 139. 356. 88. 1117. 1285700200184 223. 0.60 0.625 1285700200185 1285700200186 220.0 229. 44. 1285700200187 1285700200188 1285700200189 221.5 866. 62. 1285700200190 1285700200191 1285700200192 225.3 763. 74. 198. 30. 1226. 1285700200193 120. -0.13 0.625 1285700200194 1285700200195 ENDDATA 168 0 1285700200196 ENDSUBENT 195 0 1285700299999 SUBENT 12857003 20120710 13841285700300001 BIB 6 15 1285700300002 REACTION 1(17-CL-37(N,0),,EN) 1285700300003 2(17-CL-37(N,G),,WID/STR) 1285700300004 3(17-CL-37(N,EL),,WID,,G) 1285700300005 4(17-CL-37(N,G),,WID) 1285700300006 5(17-CL-37(N,0),,J) 1285700300007 SAMPLE (17-CL-37,ENR=0.9821) A 98.21% enriched 37Cl sample 1285700300008 was used which was 25.4 mm diam x 2.0 mm thick and 1285700300009 weighed 2.573 g. 1285700300010 ASSUMED (ASSUM,17-CL-37(N,EL),,WID,,G) g*neutron width 1285700300011 adopted from Singh+PR/C10,2138,1971 1285700300012 REL-REF (R,10518003,U.N.Singh+,J,PR/C,10,2138,1974) 1285700300013 MISC-COL (MISC) Correlation coefficient between neutron width 1285700300014 and capture width 1285700300015 HISTORY (20120710A) SD: SF6=ARE was changed to WID/STR in 1285700300016 REACTION code 2 1285700300017 ENDBIB 15 0 1285700300018 NOCOMMON 0 0 1285700300019 DATA 11 12 1285700300020 DATA 1DATA 2ERR-S 2DATA 3ERR-S 3DATA 41285700300021 ERR-S 4DATA 5MISC ASSUM STAT-W G 1285700300022 KEV MILLI-EV MILLI-EV EV EV MILLI-EV 1285700300023 MILLI-EV NO-DIM NO-DIM EV NO-DIM 1285700300024 8.303 155. 4. 58. 2. 248. 1285700300025 6. 2. 0.49 1285700300026 25.53 174. 29. 289. 32. 510. 1285700300027 67. 1. 0.79 1285700300028 27.83 39. 2. 63. 1285700300029 4. 2.5 0.625 1285700300030 42.38 58. 4. 1285700300031 1285700300032 46.49 222. 38. 355. 1285700300033 61. 2. 268. 1285700300034 55.13 43. 8. 69. 1285700300035 13. 10. 0.625 1285700300036 55.40 92. 17. 148. 1285700300037 20. 64. 0.625 1285700300038 66.84 132. 14. 212. 1285700300039 22. 33. 0.625 1285700300040 86.24 96. 14. 1285700300041 1285700300042 92.81 172. 53. 275. 1285700300043 84. 404. 0.625 1285700300044 127.3 222. 55. 355. 1285700300045 88. 215. 0.625 1285700300046 150.7 317. 53. 1285700300047 1285700300048 ENDDATA 28 0 1285700300049 ENDSUBENT 48 0 1285700399999 SUBENT 12857004 20120710 13841285700400001 BIB 2 4 1285700400002 REACTION (17-CL-35(N,G)17-CL-36,,SIG,,MXW) 1285700400003 The capture cross section averaged over a 30 keV kT 1285700400004 Maxwellian spectrum 1285700400005 STATUS (TABLE) From the text of Phys.Rev. 29,1996,1984 1285700400006 ENDBIB 4 0 1285700400007 NOCOMMON 0 0 1285700400008 DATA 3 1 1285700400009 KT DATA DATA-ERR 1285700400010 KEV MB MB 1285700400011 30. 10.0 0.3 1285700400012 ENDDATA 3 0 1285700400013 ENDSUBENT 12 0 1285700499999 SUBENT 12857005 20120710 13841285700500001 BIB 2 4 1285700500002 REACTION (17-CL-37(N,G)17-CL-38,,SIG,,MXW) 1285700500003 The capture cross section averaged over a 30 keV kT 1285700500004 Maxwellian spectrum 1285700500005 STATUS (TABLE) From the text of Phys.Rev. 29,1996,1984 1285700500006 ENDBIB 4 0 1285700500007 NOCOMMON 0 0 1285700500008 DATA 3 1 1285700500009 KT DATA DATA-ERR 1285700500010 KEV MB MB 1285700500011 30. 2.15 0.08 1285700500012 ENDDATA 3 0 1285700500013 ENDSUBENT 12 0 1285700599999 ENDENTRY 5 0 1285799999999