ENTRY 21193 20230130 2119300000001 SUBENT 21193001 20230130 20231011 2119300100001 BIB 9 32 2119300100002 TITLE The (n,gamma) cross-section of Au-197 at 30 and 64 keV2119300100003 neutron energy 2119300100004 AUTHOR (W.Poenitz) 2119300100005 REFERENCE (J,JNE/AB,20,825,1966) 2119300100006 (C,66PARIS,1,277,1966) 2119300100007 (R,EANDC-33,164,1963) full paper of 66PARIS. 2119300100008 (R,EANDC-33,87,1963) See also. 2119300100009 (R,KFK-454,1966) Reprint of 66PARIS. 2119300100010 (R,KFK-505,1966) 2119300100011 (P,EANDC(E)-66U,5,1966) Prelim.results 2119300100012 INSTITUTE (2GERKFK,2GERKRU) 2119300100013 FACILITY (VDG,2GERKFK) 3 MeV Van de Graaff. 2119300100014 INC-SOURCE (P-LI7) Protons on Li-F target evaporated on a 0.06 cm 2119300100015 thick Cu backing for neutron energy of 30 keV. 2119300100016 (P-T) For neutron energy of 64 keV. 2119300100017 Proton beam current 150 micro-Amps. 2119300100018 Proton energy set just above the threshold of each 2119300100019 reaction to produce kinematically collimated neutrons.2119300100020 SAMPLE The gold sample of 1.8 cm diameter is exposed to the 2119300100021 neutron flux at the back of the Cu target backing. 2119300100022 DETECTOR (NAICR) NaI(Tl) crystal to measure gamma activity of 2119300100023 the sample, gamma activity of the target, and 2119300100024 activity of a well defined amount of Mn-SO4 2119300100025 solution in the manganese bath. 2119300100026 HISTORY (19791126T) 2119300100027 (19800331A) Name corrected, data set added from paris 2119300100028 conference. 2119300100029 (19810508A) ERR-ANALYS corrected. 2119300100030 (20000102U) Corrected by S.M. 2119300100031 (20060809U) Reference code corrected 2119300100032 (20230130A) SD:Updated to new date formats,lower case. 2119300100033 Corrections in all Subents. 2119300100034 ENDBIB 32 0 2119300100035 NOCOMMON 0 0 2119300100036 ENDSUBENT 35 0 2119300199999 SUBENT 21193002 20230130 20231011 2119300200001 BIB 8 26 2119300200002 REACTION (79-AU-197(N,G)79-AU-198,,SIG) 2119300200003 DECAY-DATA (79-AU-198-G,2.97D,DG,411.) 2119300200004 METHOD (ACTIV) Cross-section measured using activation method 2119300200005 for flux monitor. 2119300200006 The principle of this method is to determine the 2119300200007 neutron flux strength by the radioactivity of the 2119300200008 reaction product 7Be in the LiF target. In this case, 2119300200009 it is of special advantage, that the y-ray energies 2119300200010 occurring in the decays of 7Be and l98Au are very 2119300200011 similar and therefore the ratio of the 2119300200012 gamma-efficiencies of the used NaI(Tl) detector is 2119300200013 near to one. 2119300200014 REL-REF (M,,J.E.Perry,B,FAST N.PH.,1,1,1960) - description of 2119300200015 the method 2119300200016 COMMENT Cross-section is average of two measurements. 2119300200017 STATUS (TABLE) Text on p.829 of J.Nucl.En.,A/B,20(1966)825 2119300200018 (COREL,21193003) Flux determined by Mn bath 2119300200019 ERR-ANALYS (ERR-S) Statistical error 2119300200020 (ERR-1) Decay data uncertainty 2119300200021 (ERR-2) Shielding and absorption uncertainties in the 2119300200022 sample 2119300200023 (ERR-3) uncertainty in loss of neutrons in the target, 2119300200024 (ERR-T) total uncertainty 2119300200025 Comprehensive breakdown of errors in table 1C of the 2119300200026 publication. 2119300200027 HISTORY (20230130U) SD: BIB updated. 2119300200028 ENDBIB 26 0 2119300200029 NOCOMMON 0 0 2119300200030 DATA 7 1 2119300200031 EN DATA ERR-S ERR-1 ERR-2 ERR-3 2119300200032 ERR-T 2119300200033 KEV B PER-CENT PER-CENT PER-CENT PER-CENT 2119300200034 PER-CENT 2119300200035 30. 0.593 0.6 1.7 1.1 0.32119300200036 2.1 2119300200037 ENDDATA 6 0 2119300200038 ENDSUBENT 37 0 2119300299999 SUBENT 21193003 20230130 20231011 2119300300001 BIB 7 18 2119300300002 REACTION (79-AU-197(N,G)79-AU-198,,SIG) 2119300300003 DECAY-DATA (79-AU-198-G,2.69D,DG,411.) 2119300300004 METHOD (MANGB) The principle of this method is to determine 2119300300005 the neutron flux by the manganese bath method. The 2119300300006 radioactivity of the Au sample was determined 2119300300007 absolutely by the coincidence method. 2119300300008 REL-REF (M,,J.E.Perry,B,FAST N.PH.,1,1,1960) - description of 2119300300009 the method 2119300300010 STATUS (TABLE) Text on p.832 of J.Nucl.En.,A/B,20(1966)825 2119300300011 (COREL,21193002) Flux determined 7Be activity 2119300300012 ERR-ANALYS (ERR-S) Statistical uncertainty, 2119300300013 (ERR-1) detector efficiency uncertainty, 2119300300014 (ERR-2) sample self-shielding uncertainty, 2119300300015 (ERR-3) neutron loss uncertainty, 2119300300016 (ERR-T) total uncertainty. 2119300300017 Comprehensive breakdown of errors in table 2C of the 2119300300018 publication. 2119300300019 HISTORY (20230130U) SD: BIB updated. 2119300300020 ENDBIB 18 0 2119300300021 COMMON 4 3 2119300300022 ERR-S ERR-1 ERR-2 ERR-3 2119300300023 PER-CENT PER-CENT PER-CENT PER-CENT 2119300300024 0.6 1.2 0.5 1.7 2119300300025 ENDCOMMON 3 0 2119300300026 DATA 3 2 2119300300027 EN DATA ERR-T 2119300300028 KEV B B 2119300300029 30. 0.604 0.011 2119300300030 64. 0.360 0.008 2119300300031 ENDDATA 4 0 2119300300032 ENDSUBENT 31 0 2119300399999 SUBENT 21193004 20230130 20231011 2119300400001 BIB 4 8 2119300400002 REACTION ((79-AU-197(N,G)79-AU-198,,SIG)// 2119300400003 (79-AU-197(N,G)79-AU-198,,SIG)) 2119300400004 ANALYSIS Ratio of cross-section at 30 keV to that at 64 keV 2119300400005 from measurements made using manganese bath for flux 2119300400006 measurement. 2119300400007 STATUS (TABLE) table 3 of J.Nucl.En.,A/B,20(1966)825 2119300400008 HISTORY (20230130A) SD: SF4=Au-198g -> Au-198 in REACTION code.2119300400009 BIB updated. 2119300400010 ENDBIB 8 0 2119300400011 NOCOMMON 0 0 2119300400012 DATA 3 1 2119300400013 EN-NM EN-DN DATA 2119300400014 KEV KEV NO-DIM 2119300400015 30. 64. 1.676 2119300400016 ENDDATA 3 0 2119300400017 ENDSUBENT 16 0 2119300499999 SUBENT 21193005 20230130 20231011 2119300500001 BIB 5 13 2119300500002 REACTION (79-AU-197(N,G)79-AU-198,,SIG,,AV) 2119300500003 ANALYSIS Average value of cross-section measured using 2119300500004 activation and manganese bath to measure the flux. 2119300500005 ERR-ANALYS (ERR-1) Calculated assuming that the difference 2119300500006 between the results of the manganese bath 2119300500007 method and the activation method of flux 2119300500008 measurement are due to systematic errors. 2119300500009 (ERR-S) Calculated assuming that the difference 2119300500010 between these two methods are due to 2119300500011 random errors. 2119300500012 STATUS (TABLE) Text on p.832 of J.Nucl.En.,A/B,20(1966)825 2119300500013 HISTORY (20230130A) SD: SF4=Au-198g -> Au-198; SF8=AV added to 2119300500014 REACTION code. BIB updated. 2119300500015 ENDBIB 13 0 2119300500016 NOCOMMON 0 0 2119300500017 DATA 4 1 2119300500018 EN DATA ERR-1 ERR-S 2119300500019 KEV B B B 2119300500020 30. 0.600 0.012 0.009 2119300500021 ENDDATA 3 0 2119300500022 ENDSUBENT 21 0 2119300599999 SUBENT 21193006 20230130 20231011 2119300600001 BIB 6 20 2119300600002 REACTION (79-AU-197(N,G)79-AU-198,,SIG) 2119300600003 ANALYSIS Data derived from average cross-section at 30 keV of 2119300600004 manganese bath and activation flux measurements using 2119300600005 the average ratio between this and the 64 keV cross- 2119300600006 section from present and previous measurements. 2119300600007 ASSUMED (ASSUM,79-AU-197(N,G)79-AU-198-G,,SIG,,REL) Cross- 2119300600008 section at 30 keV relative to that at 64 keV taken as 2119300600009 mean of value from this work and two previous works. 2119300600010 ERR-ANALYS (ERR-1) Calculated assuming that the difference 2119300600011 between the results of the manganese bath 2119300600012 method and the activation method of flux 2119300600013 measurement are due to systematic errors. 2119300600014 (ERR-S) Calculated assuming that the difference 2119300600015 between these two methods are due to 2119300600016 random errors. 2119300600017 STATUS (TABLE) Text on p.833 of J.Nucl.En.,A/B,20(1966)825 2119300600018 (DEP,21193003) 2119300600019 (DEP,21193005) 2119300600020 HISTORY (20230130A) SD: SF4=Au-198g -> Au-198 in REACTION code.2119300600021 BIB updated. 2119300600022 ENDBIB 20 0 2119300600023 COMMON 1 3 2119300600024 ASSUM 2119300600025 ARB-UNITS 2119300600026 1.679 2119300600027 ENDCOMMON 3 0 2119300600028 DATA 4 1 2119300600029 EN DATA ERR-1 ERR-S 2119300600030 KEV B B B 2119300600031 64. 0.357 0.014 0.009 2119300600032 ENDDATA 3 0 2119300600033 ENDSUBENT 32 0 2119300699999 SUBENT 21193007 20230130 20231011 2119300700001 BIB 5 11 2119300700002 REACTION (79-AU-197(N,G)79-AU-198,,SIG) 2119300700003 COMMENT Independent measurement done with the same experimental2119300700004 mental method as the one of Subent 002, but with a 2119300700005 better geometric arrangement of the target and the 2119300700006 manganese bath, resulting in a smaller loss of neutrons2119300700007 due to leakage at the edge of the manganese bath. 2119300700008 ERR-ANALYS (DATA-ERR) No information about source of uncertainty 2119300700009 STATUS (TABLE) Text on p.4 of KFK-454 2119300700010 HISTORY (19800331A) G.C. Added data set from paris conference. 2119300700011 (20230130A) SD: SF4=Au-198g -> Au-198 in REACTION code.2119300700012 BIB updated. 2119300700013 ENDBIB 11 0 2119300700014 NOCOMMON 0 0 2119300700015 DATA 3 1 2119300700016 EN DATA DATA-ERR 2119300700017 KEV B B 2119300700018 30. 0.598 0.012 2119300700019 ENDDATA 3 0 2119300700020 ENDSUBENT 19 0 2119300799999 ENDENTRY 7 0 2119399999999