ENTRY 22908 20130203 22342290800000001 SUBENT 22908001 20130203 22342290800100001 BIB 18 54 2290800100002 TITLE New Kr-cross sections and astrophysical constraints 2290800100003 on presolar grains 2290800100004 AUTHOR (P.Mutti,H.Beer,A.Brusegan,F.Corvi,R.Gallino) 2290800100005 INSTITUTE (2FR ILL) Mutti 2290800100006 (2GERKFK) Beer 2290800100007 (2ZZZGEL) Brusegan, Corvi 2290800100008 (2ITYTUR) Gallino. Torino University, Torino, Italy. 2290800100009 REFERENCE (C,2004SANTA,,1327,2004) Main ref, data are given 2290800100010 REL-REF (M,,F.Corvi+,J,NSE,107,272,1991) Method of data 2290800100011 analysis using the experimental-weighting function 2290800100012 FACILITY (LINAC,2ZZZGEL) Geel linear accelerator 'GELINA' 2290800100013 INC-SOURCE The neutron flux was generated by electron bursts of 2290800100014 100-MeV average energy, 1-ns width, at a repetition 2290800100015 rate of 800-Hz and average beam current of 75-muA, 2290800100016 hitting a mercury-cooled rotary uranium target. 2290800100017 METHOD (TOF) 2290800100018 PART-DET (G) 2290800100019 DETECTOR (SCIN).Gamma rays were detected by C(6)D(6)-based 2290800100020 liquid scintillators. 2290800100021 (GLASD) For the total cross section measurement, the 2290800100022 moderated neutrons, were detected by a 1/4-inch thick 2290800100023 Li-glass (NE912). 2290800100024 (BF3) three BF(3) proportional counters were used as 2290800100025 neutron-flux monitors during the measuring time. 2290800100026 ANALYSIS .The Maxwell averaged calculations were performed 2290800100027 using new resonance parameters up to 5-keV. 2290800100028 .Resonance parameters deduced from the measured total 2290800100029 Krypton isotopes cross sections 2290800100030 INC-SPECT .Maxwell energy distribution 2290800100031 MONITOR (54-XE-131(N,0),,EN) Resonances at 46.0, 75.6 and 2290800100032 114.9 eV were used 2290800100033 MONIT-REF (,P.Ribon,R,CEA-N-1149,1969) Tech.Rep. N-1149, CEA,19692290800100034 SAMPLE For the capture measurements were used 11.05-g of 2290800100035 99.3% Kr-82 enriched gas, 17.35-g of 99.5% Kr-84 2290800100036 enriched gas and 18.03-g of 99.9% Kr-86 enriched gas. 2290800100037 In addition, three other samples were prepared, one 2290800100038 filled with N(2) to be used as a dummy sample, 2290800100039 in order to clearly identify all the structures due to 2290800100040 the alloy of the container. Another one was filled with2290800100041 natural xenon and used for normalization purposes and 2290800100042 a last one was filled with 25.87-g of natural krypton. 2290800100043 COMMENT *By authors*.In order to improve the uncertainty on the2290800100044 normalization, was performed a dedicated total cross 2290800100045 section measurement using a natural xenon sample. 2290800100046 Subsequently the data have been normalized using three 2290800100047 different resonances of Xe-131. The three obtained 2290800100048 normalisation factors agreed within 1% and the averaged2290800100049 value was then adopted. 2290800100050 STATUS (TABLE) .Table 1 of 2004SANTA,,1327,2004 2290800100051 (COREL,22692001) 2290800100052 HISTORY (20051021C) 2290800100053 (20051031U) Last checking has been done. 2290800100054 (20130203A) SD: EN-MEAN -> KT in Subents 002 - 006. 2290800100055 ERR-ANALYS moved to Subents 002-006. 2290800100056 ENDBIB 54 0 2290800100057 NOCOMMON 0 0 2290800100058 ENDSUBENT 57 0 2290800199999 SUBENT 22908002 20130203 22342290800200001 BIB 3 9 2290800200002 REACTION (36-KR-80(N,G)36-KR-81,,SIG,,MXW) 2290800200003 In the case of the two 80Kr and 83Kr isotopes, 2290800200004 the MACS calculations were performed using new 2290800200005 resonance parameters (obtained by authors) up to 2290800200006 5 keV as a complement for the average cross-section 2290800200007 data from Walter, G., etc. Nucl.Sci.Eng.,93,357(1986).2290800200008 ERR-ANALYS (ERR-S). The quoted uncertainties for Kr-80 2290800200009 and Kr-83 represent only the statistical ones. 2290800200010 HISTORY (20130203A) SD: EN-MEAN -> KT. ERR-ANALYS was added. 2290800200011 ENDBIB 9 0 2290800200012 NOCOMMON 0 0 2290800200013 DATA 3 11 2290800200014 KT DATA ERR-S 2290800200015 KEV MB MB 2290800200016 5. 992. 48. 2290800200017 10. 583. 14. 2290800200018 15. 444. 7. 2290800200019 20. 370. 4. 2290800200020 25. 323. 3. 2290800200021 30. 290. 2. 2290800200022 40. 246. 2. 2290800200023 50. 218. 1. 2290800200024 60. 197. 2. 2290800200025 80. 168. 2. 2290800200026 100. 146. 2. 2290800200027 ENDDATA 13 0 2290800200028 ENDSUBENT 27 0 2290800299999 SUBENT 22908003 20130203 22342290800300001 BIB 3 15 2290800300002 REACTION (36-KR-82(N,G)36-KR-83,,SIG,,MXW) 2290800300003 ERR-ANALYS (ERR-T).The error is reported by authors in table. 2290800300004 The uncertainty reported in table represent quadratic 2290800300005 sum of the contributions from 2290800300006 * the statistical errors on both the resonance 2290800300007 parameters and the average cross section 2290800300008 (ERR-1) 2% relative error due to the uncertainties in 2290800300009 the normalization. 2290800300010 (ERR-2,6.,10.) Error in the energy dependence of the 2290800300011 neutron flux ranging from 0 at 1-keV to 6% at 400-keV 2290800300012 with log-E interpolation, an estimated 10% error on 2290800300013 the average capture cross section due to uncertainty 2290800300014 in the back-ground subtraction and 2290800300015 (ERR-3) 5% error on the weighting procedure. 2290800300016 HISTORY (20130203A) SD: EN-MEAN -> KT. 2290800300017 ENDBIB 15 0 2290800300018 COMMON 2 3 2290800300019 ERR-1 ERR-3 2290800300020 PER-CENT PER-CENT 2290800300021 2. 5. 2290800300022 ENDCOMMON 3 0 2290800300023 DATA 3 11 2290800300024 KT DATA ERR-T 2290800300025 KEV MB MB 2290800300026 5. 263. 15. 2290800300027 10. 177. 10. 2290800300028 15. 138. 8. 2290800300029 20. 117. 7. 2290800300030 25. 103. 6. 2290800300031 30. 93. 6. 2290800300032 40. 81. 5. 2290800300033 50. 73. 5. 2290800300034 60. 68. 4. 2290800300035 80. 60. 4. 2290800300036 100. 54. 3. 2290800300037 ENDDATA 13 0 2290800300038 ENDSUBENT 37 0 2290800399999 SUBENT 22908004 20130203 22342290800400001 BIB 2 8 2290800400002 REACTION (36-KR-83(N,G)36-KR-84,,SIG,,MXW) 2290800400003 In the case of the two 80Kr and 83Kr isotopes, 2290800400004 the MACS calculations were performed using new 2290800400005 resonance parameters (obtained by authors) up to 2290800400006 5 keV as a complement for the average cross-section 2290800400007 data from Walter, G., etc. Nucl.Sci.Eng.,93,357(1986).2290800400008 ERR-ANALYS (ERR-S). The quoted uncertainties for Kr-80 2290800400009 and Kr-83 represent only the statistical ones. 2290800400010 ENDBIB 8 0 2290800400011 NOCOMMON 0 0 2290800400012 DATA 3 11 2290800400013 KT DATA ERR-S 2290800400014 KEV MB MB 2290800400015 5. 810. 44. 2290800400016 10. 539. 18. 2290800400017 15. 414. 10. 2290800400018 20. 340. 7. 2290800400019 25. 291. 5. 2290800400020 30. 255. 4. 2290800400021 40. 208. 2. 2290800400022 50. 177. 2. 2290800400023 60. 154. 2. 2290800400024 80. 123. 2. 2290800400025 100. 102. 2. 2290800400026 ENDDATA 13 0 2290800400027 ENDSUBENT 26 0 2290800499999 SUBENT 22908005 20130203 22342290800500001 BIB 3 15 2290800500002 REACTION (36-KR-84(N,G)36-KR-85,,SIG,,MXW) 2290800500003 ERR-ANALYS (ERR-T).The error is reported by authors in table. 2290800500004 The uncertainty reported in table represent quadratic 2290800500005 sum of the contributions from 2290800500006 * the statistical errors on both the resonance 2290800500007 parameters and the average cross section 2290800500008 (ERR-1) 2% relative error due to the uncertainties in 2290800500009 the normalization. 2290800500010 (ERR-2,6.,10.) Error in the energy dependence of the 2290800500011 neutron flux ranging from 0 at 1-keV to 6% at 400-keV 2290800500012 with log-E interpolation, an estimated 10% error on 2290800500013 the average capture cross section due to uncertainty 2290800500014 in the back-ground subtraction and 2290800500015 (ERR-3) 5% error on the weighting procedure. 2290800500016 HISTORY (20130203A) SD: EN-MEAN -> KT. 2290800500017 ENDBIB 15 0 2290800500018 COMMON 2 3 2290800500019 ERR-1 ERR-3 2290800500020 PER-CENT PER-CENT 2290800500021 2. 5. 2290800500022 ENDCOMMON 3 0 2290800500023 DATA 3 11 2290800500024 KT DATA ERR-T 2290800500025 KEV MB MB 2290800500026 5. 134. 7. 2290800500027 10. 74. 4. 2290800500028 15. 53. 3. 2290800500029 20. 43. 3. 2290800500030 25. 37. 2. 2290800500031 30. 33. 2. 2290800500032 40. 28. 2. 2290800500033 50. 25. 2. 2290800500034 60. 23. 2. 2290800500035 80. 20. 1. 2290800500036 100. 18. 1. 2290800500037 ENDDATA 13 0 2290800500038 ENDSUBENT 37 0 2290800599999 SUBENT 22908006 20130203 22342290800600001 BIB 3 15 2290800600002 REACTION (36-KR-86(N,G)36-KR-87,,SIG,,MXW) 2290800600003 ERR-ANALYS (ERR-T).The error is reported by authors in table. 2290800600004 The uncertainty reported in table represent quadratic 2290800600005 sum of the contributions from 2290800600006 * the statistical errors on both the resonance 2290800600007 parameters and the average cross section 2290800600008 (ERR-1) 2% relative error due to the uncertainties in 2290800600009 the normalization. 2290800600010 (ERR-2,6.,10.) Error in the energy dependence of the 2290800600011 neutron flux ranging from 0 at 1-keV to 6% at 400-keV 2290800600012 with log-E interpolation, an estimated 10% error on 2290800600013 the average capture cross section due to uncertainty 2290800600014 in the back-ground subtraction and 2290800600015 (ERR-3) 5% error on the weighting procedure. 2290800600016 HISTORY (20130203A) SD: EN-MEAN -> KT. 2290800600017 ENDBIB 15 0 2290800600018 COMMON 2 3 2290800600019 ERR-1 ERR-3 2290800600020 PER-CENT PER-CENT 2290800600021 2. 5. 2290800600022 ENDCOMMON 3 0 2290800600023 DATA 3 11 2290800600024 KT DATA ERR-T 2290800600025 KEV MB MB 2290800600026 5. 2.93 0.16 2290800600027 10. 4.43 0.25 2290800600028 15. 5.07 0.29 2290800600029 20. 5.14 0.3 2290800600030 25. 4.98 0.3 2290800600031 30. 4.76 0.28 2290800600032 40. 4.35 0.26 2290800600033 50. 4.08 0.25 2290800600034 60. 3.91 0.25 2290800600035 80. 3.69 0.26 2290800600036 100. 3.50 0.27 2290800600037 ENDDATA 13 0 2290800600038 ENDSUBENT 37 0 2290800699999 ENDENTRY 6 0 2290899999999