ENTRY 22916 20160502 22492291600000001 SUBENT 22916001 20160502 22492291600100001 BIB 14 57 2291600100002 TITLE Stellar neutron capture cross sections of the unstable 2291600100003 S-process branching point Sm-151. 2291600100004 AUTHOR (K.Wisshak, F.Voss, F.Kaeppeler, M.Krticka, S.Raman, 2291600100005 A.Mengoni, R.Gallino) 2291600100006 INSTITUTE (2GERKFK) Wisshak, Voss, Kaeppeler, and 2291600100007 experimental site 2291600100008 (3CZRCHU) Krticka 2291600100009 (1USAORL) Raman 2291600100010 (2ZZZCER) Mengoni 2291600100011 (2ITYTUR) Gallino 2291600100012 (3AULMOU) Gallino 2291600100013 REFERENCE (J,PR/C,73,015802,2006) Main reference, data are given 2291600100014 (R,FZKA-6996,2004) First publication. 2291600100015 REL-REF (I,23272001,K.Wisshak+,J,PR/C,45,2470,199205) 2291600100016 Experimental details. Te-122,-123,-124 experiment. 2291600100017 (I,22374001,K.Wisshak+,J,PR/C,48,1401,1993) 2291600100018 Experimental details. Sm-147,148,149,150,152 data. 2291600100019 (I,,K.Wisshak+,J,NIM/A,292,595,1990) 2291600100020 Description of detector. 2291600100021 FACILITY (VDG,2GERKFK) 3.7 MV Van de Graaff accelerator. 2291600100022 METHOD (TOF) Flight path is 79 cm for capture and 260 cm for 2291600100023 total cross section measurements 2291600100024 DETECTOR (D4PI,SCIN) Karlsruhe 4pi barium fluoride detector for 2291600100025 detection of capture gamma-rays. Detector consists 2291600100026 of 42 hexagonal and pentagonal crystals forming a 2291600100027 spherical shell of BaF(2) with 10 cm inner radius 2291600100028 and 15 cm thickness. Resolution of energy is 7% 2291600100029 at 2.5 MeV, time resolution 500 picosec, peak 2291600100030 efficiency 90% at 1 MeV. The 1.8-MeV gamma-ray 2291600100031 threshold in sum energy used in the present 2291600100032 experiment corresponds to an efficiency for capture 2291600100033 events of more than 95%. 2291600100034 (GLASD) Li-6 glass detectors for neutron total cross- 2291600100035 section measurement 2291600100036 INC-SOURCE (P-LI7) Metallic Li target. 2291600100037 INC-SPECT .Proton beam energy adjusted so to be 30 and 100 KeV 2291600100038 above the Li-7(P,N)be-7 reaction threshold 1.881 MeV. 2291600100039 SAMPLE .Au-197 sample 10 mm diameter, 0.4 mm = 2.1621E-3 2291600100040 atoms/B thickness, 0.5554-gram weight, enclosing 2291600100041 in welded titanium can, lid and body deep-drawn from 2291600100042 0.25-mm thick foils- 0.4329g 2291600100043 .Empty welded titanium can, lid and body deep-drawn 2291600100044 from 0.25-mm thick foils- 0.4181g 2291600100045 CORRECTION .Corrections were made for multiple scattering, 2291600100046 for isotopic impurities, for neutron self-absorption, 2291600100047 for undetected events, for signal/background ratio - 2291600100048 all for different neutron energies-these corrections 2291600100049 are smaller than 2%. 2291600100050 ERR-ANALYS (ERR-1) Error due to flight path. 2291600100051 (ERR-2) Error due to neutron flux normalization 2291600100052 (ERR-3) Error due to sample mass and elemental 2291600100053 impurities 2291600100054 HISTORY (20060507C) SM 2291600100055 (20060911U) Last corrections have been done. 2291600100056 (20160502A) M.M. Ref. FZKA-6996,2004 was added. 2291600100057 STATUS was added in data Subents. 2291600100058 Some errors were moved in proper Subents. 2291600100059 ENDBIB 57 0 2291600100060 COMMON 3 3 2291600100061 ERR-1 ERR-2 ERR-3 2291600100062 PER-CENT PER-CENT PER-CENT 2291600100063 0.1 0.2 0.2 2291600100064 ENDCOMMON 3 0 2291600100065 ENDSUBENT 64 0 2291600199999 SUBENT 22916002 20160502 22492291600200001 BIB 6 24 2291600200002 REACTION (6-C-12(N,TOT),,SIG,,AV) Averaged over 2291600200003 energy interval given in data section 2291600200004 REL-REF (A,21374000,K.Wisshak+,J,PR/C,48,1401,1993) 2291600200005 SAMPLE .Graphite sample 10 mm diameter, 1.0 mm = 8.7427-3 2291600200006 atoms/B thickness, 0.1370 gram weight, enclosing 2291600200007 welded titanium can, lid and body deep-drawn from 2291600200008 0.25-mm thick foils- 0.4349g 2291600200009 ERR-ANALYS (ERR-T) Total error. 2291600200010 COMMENT *By authors*.For easier comparison of the individual 2291600200011 results the averaged total cross sections in the 2291600200012 neutron energy interval from 10 to 100-KeV are 2291600200013 indicated as well-4.44 barns. 2291600200014 STATUS (TABLE) Table III of PR/C,73,015802,2006 2291600200015 Table 5 of FZKA-6996,2004. 2291600200016 (COREL,22307006) C12 - 3.1960g, irradiation with Ba 2291600200017 (COREL,22374023) C12 - 1.2096g, irradiation with Sm 2291600200018 (COREL,22377008) C12 - 0.909g, irradiation with Sn 2291600200019 (COREL,22386026) C12 - 0.7644g, irradiation with Gd 2291600200020 (COREL,22388026) C12 - 0.9091g, irradiation with Nd 2291600200021 (COREL,22498026) C12 - 0.7644g, irradiation with Pr,Dy 2291600200022 (COREL,22499026) C12 - 0.7651g, irradiation with Yb 2291600200023 (COREL,22813026) C12 - 0.4710g, irradiation with Cd 2291600200024 (COREL,22917002) C12 - 0.6213g, irradiation with Lu 2291600200025 (COREL,22926002) C12 - 0.6213g, irradiation with Hf 2291600200026 ENDBIB 24 0 2291600200027 COMMON 1 3 2291600200028 ERR-T 2291600200029 PER-CENT 2291600200030 1.2 2291600200031 ENDCOMMON 3 0 2291600200032 DATA 3 10 2291600200033 EN-MIN EN-MAX DATA 2291600200034 KEV KEV B 2291600200035 10. 15. 4.74 2291600200036 10. 100. 4.49 2291600200037 15. 20. 4.58 2291600200038 20. 30. 4.78 2291600200039 30. 40. 4.31 2291600200040 40. 60. 4.61 2291600200041 60. 80. 4.33 2291600200042 80. 100. 4.37 2291600200043 100. 150. 4.14 2291600200044 150. 200. 3.95 2291600200045 ENDDATA 12 0 2291600200046 ENDSUBENT 45 0 2291600299999 SUBENT 22916003 20160502 22492291600300001 BIB 5 28 2291600300002 REACTION (62-SM-151(N,TOT),,SIG,,AV) 2291600300003 averaged over energy interval given in data section 2291600300004 SAMPLE .A 206.4 mg samples of samarium oxide Sm2-O3 with 90% 2291600300005 enrichment in Sm-151 were used. It was pressed into 2291600300006 a solid pellet 10 mm in diameter, which was enclosed 2291600300007 in a titanium can prepared from 0.25 mm thick foil 2291600300008 0.4340g weight. Thickness is 0.6 mm=0.8861E-3 at/B. 2291600300009 The can consisted of a deep-drawn body 15 mm in 2291600300010 diameter with a 3 mm deep depression for the sample. 2291600300011 The lid had a corresponding depression of 1 mm to 2291600300012 match the 2-mm thick sample. An identical sample was 2291600300013 prepared from natural samarium oxide to verify the 2291600300014 experimental procedures by checking whether the cross 2291600300015 section of natural samarium could be properly 2291600300016 reproduced. 2291600300017 COMMENT *By authors*.For easier comparison of the individual 2291600300018 results the averaged total cross sections in the 2291600300019 neutron energy interval from 10 to 100-keV are 2291600300020 indicated as well-17.2 barns. 2291600300021 ERR-ANALYS (ERR-4) Error due to isotopic composition Sm-151 2291600300022 (ERR-5) Error due to isotopic correction Sm-151 2291600300023 (ERR-6) Error due to multiple scattering and self- 2291600300024 shielding-F2 cross section ratio-Sm-151. 2291600300025 (ERR-8) Error in undetected events-F1 cross section 2291600300026 ratio for Sm-151. 2291600300027 (ERR-T) Total error. 2291600300028 STATUS (TABLE) Table III of PR/C,73,015802,2006 2291600300029 Table 5 of FZKA-6996,2004. 2291600300030 ENDBIB 28 0 2291600300031 COMMON 5 3 2291600300032 ERR-T ERR-4 ERR-5 ERR-6 ERR-8 2291600300033 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2291600300034 2.1 0.2 1.6 0.3 0.8 2291600300035 ENDCOMMON 3 0 2291600300036 DATA 3 10 2291600300037 EN-MIN EN-MAX DATA 2291600300038 KEV KEV B 2291600300039 10. 15. 26.7 2291600300040 10. 100. 17.2 2291600300041 15. 20. 37.9 2291600300042 20. 30. 25.2 2291600300043 30. 40. 16.9 2291600300044 40. 60. 15.8 2291600300045 60. 80. 11.7 2291600300046 80. 100. 12.5 2291600300047 100. 150. 11.4 2291600300048 150. 200. 10.2 2291600300049 ENDDATA 12 0 2291600300050 ENDSUBENT 49 0 2291600399999 SUBENT 22916004 20160502 22492291600400001 BIB 4 18 2291600400002 REACTION (62-SM-0(N,TOT),,SIG,,AV) Averaged over 2291600400003 energy interval given in data section 2291600400004 SAMPLE .A 200.0 mg samples of samarium oxide Sm2-O3 with 2291600400005 natural isotopic content. Thickness is 0.6 mm = 2291600400006 0.9675E-3 atoms/B thickness. It was pressed into 2291600400007 a solid pellet 10 mm in diameter, which was enclosed 2291600400008 in a titanium can prepared from 0.25 mm thick foils. 2291600400009 enclosing welded titanium can, lid and, weight 2291600400010 0.3989g 2291600400011 ERR-ANALYS (ERR-4) Error due to isotopic composition Sm-151 2291600400012 (ERR-5) Error due to isotopic correction Sm-151 2291600400013 (ERR-7) Error due to multiple scattering and self- 2291600400014 shielding-F2 cross section ratio-Sm-natural 2291600400015 (ERR-9) Error in undetected events-F1 cross section 2291600400016 ratio for Sm-natural. 2291600400017 (ERR-T) Total error. 2291600400018 STATUS (TABLE) Table III of PR/C,73,015802,2006 2291600400019 Table 5 of FZKA-6996,2004. 2291600400020 ENDBIB 18 0 2291600400021 COMMON 5 3 2291600400022 ERR-T ERR-4 ERR-5 ERR-7 ERR-9 2291600400023 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2291600400024 2.2 0.2 1.6 0.4 0.4 2291600400025 ENDCOMMON 3 0 2291600400026 DATA 3 10 2291600400027 EN-MIN EN-MAX DATA 2291600400028 KEV KEV B 2291600400029 10. 15. 19.8 2291600400030 10. 100. 13.9 2291600400031 15. 20. 22.7 2291600400032 20. 30. 17.9 2291600400033 30. 40. 13.6 2291600400034 40. 60. 13.3 2291600400035 60. 80. 10.6 2291600400036 80. 100. 12.1 2291600400037 100. 150. 11.6 2291600400038 150. 200. 11.1 2291600400039 ENDDATA 12 0 2291600400040 ENDSUBENT 39 0 2291600499999 SUBENT 22916005 20160502 22492291600500001 BIB 4 19 2291600500002 REACTION (79-AU-197(N,TOT),,SIG,,AV) Averaged over 2291600500003 energy interval given in data section 2291600500004 ERR-ANALYS (ERR-T) Total error. 2291600500005 COMMENT *By authors*.For easier comparison of the individual 2291600500006 results the averaged total cross sections in the 2291600500007 neutron energy interval from 10 to 100-keV are 2291600500008 indicated as well-12.8 barns. 2291600500009 STATUS (TABLE) Table III of PR/C,73,015802,2006 2291600500010 Table 5 of FZKA-6996,2004. 2291600500011 (COREL,22307007) Au - 1.8709g, irradiation with Ba 2291600500012 (COREL,22374024) Au - 1.2989g, irradiation with Sm 2291600500013 (COREL,22377009) Au - 1.871 g, irradiation with Sn 2291600500014 (COREL,22386027) Au - 1.2990g, irradiation with Gd 2291600500015 (COREL,22388028) Au - 1.8709g, irradiation with Nd 2291600500016 (COREL,22498028) Au - 1.2990g, irradiation with Pr,Dy 2291600500017 (COREL,22499027) Au - 1.2995g, irradiation with Yb 2291600500018 (COREL,22813027) Au - 1.2987g, irradiation with Cd 2291600500019 (COREL,22917005) Au - 1.2996g, irradiation with Lu 2291600500020 (COREL,22926008) Au - 1.2996g, irradiation with Hf 2291600500021 ENDBIB 19 0 2291600500022 COMMON 1 3 2291600500023 ERR-T 2291600500024 PER-CENT 2291600500025 1.5 2291600500026 ENDCOMMON 3 0 2291600500027 DATA 3 10 2291600500028 EN-MIN EN-MAX DATA 2291600500029 KEV KEV B 2291600500030 10. 15. 19.0 2291600500031 10. 100. 12.8 2291600500032 15. 20. 18.5 2291600500033 20. 30. 15.1 2291600500034 30. 40. 12.7 2291600500035 40. 60. 12.3 2291600500036 60. 80. 10.5 2291600500037 80. 100. 11.4 2291600500038 100. 150. 10.4 2291600500039 150. 200. 9.1 2291600500040 ENDDATA 12 0 2291600500041 ENDSUBENT 40 0 2291600599999 SUBENT 22916006 20160502 22492291600600001 BIB 4 24 2291600600002 REACTION ((62-SM-151(N,G)62-SM-152,,SIG,,AV)/ 2291600600003 (79-AU-197(N,G)79-AU-198,,SIG,,AV)) averaged 2291600600004 over energy interval given in data section 2291600600005 SAMPLE .At the moment of the measurements - 2291600600006 Sm-151, chemical form Sm2-O3, sample 10 mm diameter, 2291600600007 0.6 mm=0.8861E-3 atoms/B thickness, 0.20216 gram 2291600600008 weight, enclosing in welded titanium can, lid and body2291600600009 deep-drawn from 0.25 mm thick foils, weight 0.4340g. 2291600600010 Sm-144 content is 0.52%, Sm-147 content is 1.398%, 2291600600011 Sm-148 content is 0.224%. Sm-149 content is 0.408%, 2291600600012 Sm-150 content is 4.013%, Sm-151 content is 89.842%, 2291600600013 Sm-152 content is 3.389%, Sm-154 content is 0.674%. 2291600600014 .Eu2-O3 admixture is 4.24 milligram 2291600600015 ERR-ANALYS (ERR-SYS) Total systematic error 2291600600016 (ERR-S) Statistical error 2291600600017 (ERR-4) Error due to isotopic composition Sm-151 2291600600018 (ERR-5) Error due to isotopic correction Sm-151 2291600600019 (ERR-6) Error due to multiple scattering and self- 2291600600020 shielding-F2 cross section ratio-Sm-151. 2291600600021 (ERR-8) Error in undetected events-F1 cross section 2291600600022 ratio for Sm-151. 2291600600023 (ERR-T) Total error. 2291600600024 STATUS (TABLE) Table V of PR/C,73,015802,2006 2291600600025 Table 13 of FZKA-6996,2004. 2291600600026 ENDBIB 24 0 2291600600027 COMMON 5 3 2291600600028 ERR-SYS ERR-4 ERR-5 ERR-6 ERR-8 2291600600029 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2291600600030 1.9 0.2 1.6 0.3 0.8 2291600600031 ENDCOMMON 3 0 2291600600032 DATA 5 18 2291600600033 EN-MIN EN-MAX DATA ERR-S ERR-T 2291600600034 KEV KEV NO-DIM PER-CENT PER-CENT 2291600600035 3. 5. 5.1766 17. 17. 2291600600036 5. 7.5 4.5172 7.5 7.7 2291600600037 7.5 10. 4.4857 5.6 5.9 2291600600038 10. 12.5 5.3337 4. 4.4 2291600600039 12.5 15. 5.6682 3.5 4. 2291600600040 15. 20. 5.5837 2. 2.8 2291600600041 20. 25. 6.1048 1.7 2.5 2291600600042 25. 30. 5.6615 1.5 2.4 2291600600043 30. 40. 5.6217 1.2 2.2 2291600600044 40. 50. 5.6438 1.2 2.2 2291600600045 50. 60. 5.6083 1.2 2.2 2291600600046 60. 80. 5.1157 1.1 2.2 2291600600047 80. 100. 4.7008 1.1 2.2 2291600600048 100. 120. 4.3067 1.1 2.2 2291600600049 120. 150. 3.9689 2.1 2.8 2291600600050 150. 175. 3.7748 2.3 3. 2291600600051 175. 200. 3.3679 2.5 3.1 2291600600052 200. 225. 3.1516 4.3 4.7 2291600600053 ENDDATA 20 0 2291600600054 ENDSUBENT 53 0 2291600699999 SUBENT 22916007 20160502 22492291600700001 BIB 4 20 2291600700002 REACTION ((62-SM-0(N,G),,SIG,,AV)/ 2291600700003 (79-AU-197(N,G)79-AU-198,,SIG,,AV)) Table V, 2291600700004 averaged over energy interval given in data section 2291600700005 SAMPLE Natural Sm-sample(chemical form Sm(2)O(3)) 10-mm 2291600700006 diameter, 0.6-mm=0.9675E-3 atoms/B thickness, 0.2200 2291600700007 gram weight, enclosing welded titanium can, lid and 2291600700008 body deep-drawn from 0.25-mm thick foils- 0.3989g 2291600700009 empty welded titanium can, lid and body deep-drawn from2291600700010 0.25-mm thick foils- 0.4181g 2291600700011 ERR-ANALYS (ERR-SYS) Total systematic error 2291600700012 (ERR-S) Statistical error 2291600700013 (ERR-4) Error due to isotopic composition Sm-151 2291600700014 (ERR-5) Error due to isotopic correction Sm-151 2291600700015 (ERR-7) Error due to multiple scattering and self- 2291600700016 shielding-F2 cross section ratio-Sm-natural 2291600700017 (ERR-9) Error in undetected events-F1 cross section 2291600700018 ratio for Sm-natural. 2291600700019 (ERR-T) Total error. 2291600700020 STATUS (TABLE) Table V of PR/C,73,015802,2006 2291600700021 Table 13 of FZKA-6996,2004. 2291600700022 ENDBIB 20 0 2291600700023 COMMON 5 3 2291600700024 ERR-SYS ERR-4 ERR-5 ERR-7 ERR-9 2291600700025 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2291600700026 0.6 0.2 1.6 0.4 0.4 2291600700027 ENDCOMMON 3 0 2291600700028 DATA 5 18 2291600700029 EN-MIN EN-MAX DATA ERR-S ERR-T 2291600700030 KEV KEV NO-DIM PER-CENT PER-CENT 2291600700031 3. 5. 0.8869 56. 56. 2291600700032 5. 7.5 0.8985 16. 16. 2291600700033 7.5 10. 0.8234 14. 14. 2291600700034 10. 12.5 0.9985 10. 10. 2291600700035 12.5 15. 0.9908 8.1 8.1 2291600700036 15. 20. 0.9469 4.5 4.5 2291600700037 20. 25. 1.1289 3.4 3.5 2291600700038 25. 30. 1.0112 3.0 3.1 2291600700039 30. 40. 0.9429 2.5 2.6 2291600700040 40. 50. 1.0150 2.4 2.5 2291600700041 50. 60. 1.0572 2.3 2.4 2291600700042 60. 80. 0.9998 2.1 2.2 2291600700043 80. 100. 1.0333 2.1 2.2 2291600700044 100. 120. 0.9961 2.1 2.2 2291600700045 120. 150. 0.9967 4. 4. 2291600700046 150. 175. 0.9955 4.3 4.3 2291600700047 175. 200. 0.9543 4.6 4.6 2291600700048 200. 225. 0.9553 8. 8. 2291600700049 ENDDATA 20 0 2291600700050 ENDSUBENT 49 0 2291600799999 SUBENT 22916008 20160502 22492291600800001 BIB 6 17 2291600800002 REACTION (62-SM-151(N,G)62-SM-152,,SIG,,AV) Averaged over 2291600800003 energy interval given in data section 2291600800004 MONITOR ((MONIT)79-AU-197(N,G)79-AU-198,,SIG) 2291600800005 MONIT-REF (,W.Ratynski+,J,PR/C,37,595,1988) 2291600800006 STATUS (TABLE) Table VI of PR/C,73,015802,2006 2291600800007 Table 14 of FZKA-6996,2004. 2291600800008 (DEP,22916006) 2291600800009 (DEP,22916007) 2291600800010 ANALYSIS . The absolute cross section was obtained 2291600800011 from the experimental ratios using the gold data of 2291600800012 Macklin(see 12720.002) after normalization by a 2291600800013 factor of 0.989 to the absolute value (see MONIT-REF) 2291600800014 ERR-ANALYS (MONIT-ERR) Error of the Au-197(N,G) monitor. 2291600800015 The uncertainties of the resulting values can be 2291600800016 obtained by adding the 1.5% uncertainty of the 2291600800017 reference cross section to the uncertainties of the 2291600800018 respective cross section ratios. 2291600800019 ENDBIB 17 0 2291600800020 COMMON 1 3 2291600800021 MONIT-ERR 2291600800022 PER-CENT 2291600800023 1.5 2291600800024 ENDCOMMON 3 0 2291600800025 DATA 4 18 2291600800026 EN-MIN EN-MAX DATA MONIT 2291600800027 KEV KEV MB MB 2291600800028 3. 5. 11734. 2267. 2291600800029 5. 7.5 7800. 1727. 2291600800030 7.5 10. 5454. 1216. 2291600800031 10. 12.5 5690. 1067. 2291600800032 12.5 15. 4977. 878. 2291600800033 15. 20. 4125. 739. 2291600800034 20. 25. 3663. 600. 2291600800035 25. 30. 3231. 571. 2291600800036 30. 40. 2813. 500. 2291600800037 40. 50. 2446. 433. 2291600800038 50. 60. 2185. 390. 2291600800039 60. 80. 1787. 349. 2291600800040 80. 100. 1402. 298. 2291600800041 100. 120. 1250. 290. 2291600800042 120. 150. 1088. 274. 2291600800043 150. 175. 995. 264. 2291600800044 175. 200. 851. 253. 2291600800045 200. 225. 783. 249. 2291600800046 ENDDATA 20 0 2291600800047 ENDSUBENT 46 0 2291600899999 SUBENT 22916009 20160502 22492291600900001 BIB 6 16 2291600900002 REACTION (62-SM-0(N,G),,SIG,,AV) 2291600900003 Averaged over energy interval given in data section 2291600900004 MONITOR ((MONIT)79-AU-197(N,G)79-AU-198,,SIG) 2291600900005 MONIT-REF (,W.Ratynski+,J,PR/C,37,595,1988) 2291600900006 STATUS (TABLE) Table VI of PR/C,73,015802,2006 2291600900007 Table 14 of FZKA-6996,2004. 2291600900008 (DEP,22916007) 2291600900009 ANALYSIS .The absolute cross section was obtained 2291600900010 from the experimental ratios using the gold data of 2291600900011 Macklin(see 12720.002) after normalization by a factor2291600900012 of 0.989 to the absolute value (see MONIT-REF) 2291600900013 ERR-ANALYS (MONIT-ERR) Error of the Au-197(N,G) monitor. 2291600900014 The uncertainties of the resulting values can be 2291600900015 obtained by adding the 1.5% uncertainty of the 2291600900016 reference cross section to the uncertainties of the 2291600900017 respective cross section ratios. 2291600900018 ENDBIB 16 0 2291600900019 COMMON 1 3 2291600900020 MONIT-ERR 2291600900021 PER-CENT 2291600900022 1.5 2291600900023 ENDCOMMON 3 0 2291600900024 DATA 4 18 2291600900025 EN-MIN EN-MAX DATA MONIT 2291600900026 KEV KEV MB MB 2291600900027 3. 5. 2010. 2267. 2291600900028 5. 7.5 1552. 1727. 2291600900029 7.5 10. 1001. 1216. 2291600900030 10. 12.5 1065. 1067. 2291600900031 12.5 15. 870. 878. 2291600900032 15. 20. 700. 739. 2291600900033 20. 25. 677. 600. 2291600900034 25. 30. 577. 571. 2291600900035 30. 40. 472. 500. 2291600900036 40. 50. 440. 433. 2291600900037 50. 60. 412. 390. 2291600900038 60. 80. 349. 349. 2291600900039 80. 100. 308. 298. 2291600900040 100. 120. 289. 290. 2291600900041 120. 150. 273. 274. 2291600900042 150. 175. 263. 264. 2291600900043 175. 200. 241. 253. 2291600900044 200. 225. 237. 249. 2291600900045 ENDDATA 20 0 2291600900046 ENDSUBENT 45 0 2291600999999 SUBENT 22916010 20160502 22492291601000001 BIB 7 32 2291601000002 REACTION (62-SM-151(N,G)62-SM-152,,SIG,,MXW) 2291601000003 INC-SPECT .Maxwellian neutron energy distribution 2291601000004 REL-REF (R,,J.Kopecky+,R,INDC(NDS)-362,1997) Data for ASSUM1, 2291601000005 ASSUM3 2291601000006 ANALYSIS The neutron energy range from thermal to 700-KeV was 2291601000007 divided into three intervals-I(X). The dominant part 2291601000008 between 3 and 225-KeV (I2) is provided by the present 2291601000009 experiments. These data were obtained with sufficient 2291601000010 resolution in neutron energy to exclude systematic 2291601000011 uncertainties in the calculation of the maxwellian 2291601000012 average. Contributions for 0-3 =I(1) and 225-700 keV 2291601000013 = I(3) are taken from REL-REF being normalized to the 2291601000014 present data. 2291601000015 ASSUMED (ASSUM1,62-SM-151(N,G)62-SM-152,PAR,SIG,,MXW,EVAL) For 2291601000016 energy range 0 - 3 keV from REL-REF 2291601000017 (ASSUM2,62-SM-151(N,G)62-SM-152,PAR,SIG,,MXW,EXP) For 2291601000018 energy range 3 keV - 225 keV obtained in this work 2291601000019 (ASSUM3,62-SM-151(N,G)62-SM-152,PAR,SIG,,MXW,EVAL) For 2291601000020 energy range 225 - 700 keV from REL-REF 2291601000021 STATUS (TABLE) Table VIII of PR/C,73,015802,2006 2291601000022 Table 16 of FZKA-6996,2004. 2291601000023 (DEP,22916006) 2291601000024 (DEP,22916008) 2291601000025 ERR-ANALYS (ERR-SYS) The systematic uncertainties of the mxw- 2291601000026 cross sections are determined by the uncertainties of 2291601000027 the measured cross section ratios in the interval I2 2291601000028 as well as by the respective I1 and I3 contributions. 2291601000029 (ERR-S) Statistical uncertainty is reported in table 2291601000030 (ERR-T) Total error as reported in Table VIII. 2291601000031 1.5% uncertainty of the gold cross section is not 2291601000032 included, since it cancels out in most applications 2291601000033 of relevance for nuclear astrophysics. 2291601000034 ENDBIB 32 0 2291601000035 NOCOMMON 0 0 2291601000036 DATA 11 14 2291601000037 KT DATA ERR-S ERR-SYS ERR-T ASSUM1 2291601000038 ASSUM1-ERR ASSUM2 ASSUM2-ERR ASSUM3 ASSUM3-ERR 2291601000039 KEV MB MB MB MB MB 2291601000040 MB MB MB MB MB 2291601000041 8. 7028. 214. 189. 285. 1384. 2291601000042 134. 5644. 203. 0. 2291601000043 10. 6082. 157. 147. 215. 923. 2291601000044 92. 5159. 150. 0. 2291601000045 15. 4704. 88. 99. 132. 434. 2291601000046 43. 4270. 85. 0. 2291601000047 20. 3925. 59. 79. 99. 251. 2291601000048 25. 3674. 58. 0.1 2291601000049 25. 3407. 45. 67. 81. 163. 2291601000050 16. 3243. 44. 0.8 2291601000051 30. 3031. 36. 59. 69. 115. 2291601000052 12. 2913. 35. 3.1 0.1 2291601000053 40. 2510. 26. 48. 55. 65.52291601000054 7. 2429. 26. 15.0 0.4 2291601000055 50. 2158. 21. 41. 46. 42.32291601000056 4. 2079. 21. 36.6 1.0 2291601000057 52. 2101. 20. 40. 45. 39.12291601000058 4. 2020. 20. 41.7 1.2 2291601000059 60. 1920. 18. 36. 40. 29.52291601000060 3. 1807. 18. 83.8 2.5 2291601000061 70. 1700. 16. 32. 36. 21.82291601000062 2. 1586. 16. 92.3 2.9 2291601000063 80. 1538. 15. 29. 33. 16.72291601000064 2. 1402. 14. 119. 4. 2291601000065 90. 1405. 14. 27. 30. 13.22291601000066 1. 1248. 13. 143. 5. 2291601000067 100. 1291. 12. 25. 28. 10.82291601000068 1. 1117. 11. 164. 6. 2291601000069 ENDDATA 32 0 2291601000070 ENDSUBENT 69 0 2291601099999 ENDENTRY 10 0 2291699999999