ENTRY 21193 20230130 231321193 0 1 SUBENT 21193001 20230130 231321193 1 1 BIB 9 32 21193 1 2 TITLE The (n,gamma) cross-section of Au-197 at 30 and 64 keV21193 1 3 neutron energy 21193 1 4 AUTHOR (W.Poenitz) 21193 1 5 REFERENCE (J,JNE/AB,20,825,1966) 21193 1 6 (C,66PARIS,1,277,1966) 21193 1 7 (R,EANDC-33,164,1963) full paper of 66PARIS. 21193 1 8 (R,EANDC-33,87,1963) See also. 21193 1 9 (R,KFK-454,1966) Reprint of 66PARIS. 21193 1 10 (R,KFK-505,1966) 21193 1 11 (P,EANDC(E)-66U,5,1966) Prelim.results 21193 1 12 INSTITUTE (2GERKFK,2GERKRU) 21193 1 13 FACILITY (VDG,2GERKFK) 3 MeV Van de Graaff. 21193 1 14 INC-SOURCE (P-LI7) Protons on Li-F target evaporated on a 0.06 cm 21193 1 15 thick Cu backing for neutron energy of 30 keV. 21193 1 16 (P-T) For neutron energy of 64 keV. 21193 1 17 Proton beam current 150 micro-Amps. 21193 1 18 Proton energy set just above the threshold of each 21193 1 19 reaction to produce kinematically collimated neutrons.21193 1 20 SAMPLE The gold sample of 1.8 cm diameter is exposed to the 21193 1 21 neutron flux at the back of the Cu target backing. 21193 1 22 DETECTOR (NAICR) NaI(Tl) crystal to measure gamma activity of 21193 1 23 the sample, gamma activity of the target, and 21193 1 24 activity of a well defined amount of Mn-SO4 21193 1 25 solution in the manganese bath. 21193 1 26 HISTORY (19791126T) 21193 1 27 (19800331A) Name corrected, data set added from paris 21193 1 28 conference. 21193 1 29 (19810508A) ERR-ANALYS corrected. 21193 1 30 (20000102U) Corrected by S.M. 21193 1 31 (20060809U) Reference code corrected 21193 1 32 (20230130A) SD:Updated to new date formats,lower case. 21193 1 33 Corrections in all Subents. 21193 1 34 ENDBIB 32 0 21193 1 35 NOCOMMON 0 0 21193 1 36 ENDSUBENT 35 0 21193 199999 SUBENT 21193002 20230130 231321193 2 1 BIB 8 26 21193 2 2 REACTION (79-AU-197(N,G)79-AU-198,,SIG) 21193 2 3 DECAY-DATA (79-AU-198-G,2.97D,DG,411.) 21193 2 4 METHOD (ACTIV) Cross-section measured using activation method 21193 2 5 for flux monitor. 21193 2 6 The principle of this method is to determine the 21193 2 7 neutron flux strength by the radioactivity of the 21193 2 8 reaction product 7Be in the LiF target. In this case, 21193 2 9 it is of special advantage, that the y-ray energies 21193 2 10 occurring in the decays of 7Be and l98Au are very 21193 2 11 similar and therefore the ratio of the 21193 2 12 gamma-efficiencies of the used NaI(Tl) detector is 21193 2 13 near to one. 21193 2 14 REL-REF (M,,J.E.Perry,B,FAST N.PH.,1,1,1960) - description of 21193 2 15 the method 21193 2 16 COMMENT Cross-section is average of two measurements. 21193 2 17 STATUS (TABLE) Text on p.829 of J.Nucl.En.,A/B,20(1966)825 21193 2 18 (COREL,21193003) Flux determined by Mn bath 21193 2 19 ERR-ANALYS (ERR-S) Statistical error 21193 2 20 (ERR-1) Decay data uncertainty 21193 2 21 (ERR-2) Shielding and absorption uncertainties in the 21193 2 22 sample 21193 2 23 (ERR-3) uncertainty in loss of neutrons in the target, 21193 2 24 (ERR-T) total uncertainty 21193 2 25 Comprehensive breakdown of errors in table 1C of the 21193 2 26 publication. 21193 2 27 HISTORY (20230130U) SD: BIB updated. 21193 2 28 ENDBIB 26 0 21193 2 29 NOCOMMON 0 0 21193 2 30 DATA 7 1 21193 2 31 EN DATA ERR-S ERR-1 ERR-2 ERR-3 21193 2 32 ERR-T 21193 2 33 KEV B PER-CENT PER-CENT PER-CENT PER-CENT 21193 2 34 PER-CENT 21193 2 35 30. 0.593 0.6 1.7 1.1 0.321193 2 36 2.1 21193 2 37 ENDDATA 6 0 21193 2 38 ENDSUBENT 37 0 21193 299999 SUBENT 21193003 20230130 231321193 3 1 BIB 7 18 21193 3 2 REACTION (79-AU-197(N,G)79-AU-198,,SIG) 21193 3 3 DECAY-DATA (79-AU-198-G,2.69D,DG,411.) 21193 3 4 METHOD (MANGB) The principle of this method is to determine 21193 3 5 the neutron flux by the manganese bath method. The 21193 3 6 radioactivity of the Au sample was determined 21193 3 7 absolutely by the coincidence method. 21193 3 8 REL-REF (M,,J.E.Perry,B,FAST N.PH.,1,1,1960) - description of 21193 3 9 the method 21193 3 10 STATUS (TABLE) Text on p.832 of J.Nucl.En.,A/B,20(1966)825 21193 3 11 (COREL,21193002) Flux determined 7Be activity 21193 3 12 ERR-ANALYS (ERR-S) Statistical uncertainty, 21193 3 13 (ERR-1) detector efficiency uncertainty, 21193 3 14 (ERR-2) sample self-shielding uncertainty, 21193 3 15 (ERR-3) neutron loss uncertainty, 21193 3 16 (ERR-T) total uncertainty. 21193 3 17 Comprehensive breakdown of errors in table 2C of the 21193 3 18 publication. 21193 3 19 HISTORY (20230130U) SD: BIB updated. 21193 3 20 ENDBIB 18 0 21193 3 21 COMMON 4 3 21193 3 22 ERR-S ERR-1 ERR-2 ERR-3 21193 3 23 PER-CENT PER-CENT PER-CENT PER-CENT 21193 3 24 0.6 1.2 0.5 1.7 21193 3 25 ENDCOMMON 3 0 21193 3 26 DATA 3 2 21193 3 27 EN DATA ERR-T 21193 3 28 KEV B B 21193 3 29 30. 0.604 0.011 21193 3 30 64. 0.360 0.008 21193 3 31 ENDDATA 4 0 21193 3 32 ENDSUBENT 31 0 21193 399999 SUBENT 21193004 20230130 231321193 4 1 BIB 4 8 21193 4 2 REACTION ((79-AU-197(N,G)79-AU-198,,SIG)// 21193 4 3 (79-AU-197(N,G)79-AU-198,,SIG)) 21193 4 4 ANALYSIS Ratio of cross-section at 30 keV to that at 64 keV 21193 4 5 from measurements made using manganese bath for flux 21193 4 6 measurement. 21193 4 7 STATUS (TABLE) table 3 of J.Nucl.En.,A/B,20(1966)825 21193 4 8 HISTORY (20230130A) SD: SF4=Au-198g -> Au-198 in REACTION code.21193 4 9 BIB updated. 21193 4 10 ENDBIB 8 0 21193 4 11 NOCOMMON 0 0 21193 4 12 DATA 3 1 21193 4 13 EN-NM EN-DN DATA 21193 4 14 KEV KEV NO-DIM 21193 4 15 30. 64. 1.676 21193 4 16 ENDDATA 3 0 21193 4 17 ENDSUBENT 16 0 21193 499999 SUBENT 21193005 20230130 231321193 5 1 BIB 5 13 21193 5 2 REACTION (79-AU-197(N,G)79-AU-198,,SIG,,AV) 21193 5 3 ANALYSIS Average value of cross-section measured using 21193 5 4 activation and manganese bath to measure the flux. 21193 5 5 ERR-ANALYS (ERR-1) Calculated assuming that the difference 21193 5 6 between the results of the manganese bath 21193 5 7 method and the activation method of flux 21193 5 8 measurement are due to systematic errors. 21193 5 9 (ERR-S) Calculated assuming that the difference 21193 5 10 between these two methods are due to 21193 5 11 random errors. 21193 5 12 STATUS (TABLE) Text on p.832 of J.Nucl.En.,A/B,20(1966)825 21193 5 13 HISTORY (20230130A) SD: SF4=Au-198g -> Au-198; SF8=AV added to 21193 5 14 REACTION code. BIB updated. 21193 5 15 ENDBIB 13 0 21193 5 16 NOCOMMON 0 0 21193 5 17 DATA 4 1 21193 5 18 EN DATA ERR-1 ERR-S 21193 5 19 KEV B B B 21193 5 20 30. 0.600 0.012 0.009 21193 5 21 ENDDATA 3 0 21193 5 22 ENDSUBENT 21 0 21193 599999 SUBENT 21193006 20230130 231321193 6 1 BIB 6 20 21193 6 2 REACTION (79-AU-197(N,G)79-AU-198,,SIG) 21193 6 3 ANALYSIS Data derived from average cross-section at 30 keV of 21193 6 4 manganese bath and activation flux measurements using 21193 6 5 the average ratio between this and the 64 keV cross- 21193 6 6 section from present and previous measurements. 21193 6 7 ASSUMED (ASSUM,79-AU-197(N,G)79-AU-198-G,,SIG,,REL) Cross- 21193 6 8 section at 30 keV relative to that at 64 keV taken as 21193 6 9 mean of value from this work and two previous works. 21193 6 10 ERR-ANALYS (ERR-1) Calculated assuming that the difference 21193 6 11 between the results of the manganese bath 21193 6 12 method and the activation method of flux 21193 6 13 measurement are due to systematic errors. 21193 6 14 (ERR-S) Calculated assuming that the difference 21193 6 15 between these two methods are due to 21193 6 16 random errors. 21193 6 17 STATUS (TABLE) Text on p.833 of J.Nucl.En.,A/B,20(1966)825 21193 6 18 (DEP,21193003) 21193 6 19 (DEP,21193005) 21193 6 20 HISTORY (20230130A) SD: SF4=Au-198g -> Au-198 in REACTION code.21193 6 21 BIB updated. 21193 6 22 ENDBIB 20 0 21193 6 23 COMMON 1 3 21193 6 24 ASSUM 21193 6 25 ARB-UNITS 21193 6 26 1.679 21193 6 27 ENDCOMMON 3 0 21193 6 28 DATA 4 1 21193 6 29 EN DATA ERR-1 ERR-S 21193 6 30 KEV B B B 21193 6 31 64. 0.357 0.014 0.009 21193 6 32 ENDDATA 3 0 21193 6 33 ENDSUBENT 32 0 21193 699999 SUBENT 21193007 20230130 231321193 7 1 BIB 5 11 21193 7 2 REACTION (79-AU-197(N,G)79-AU-198,,SIG) 21193 7 3 COMMENT Independent measurement done with the same experimental21193 7 4 mental method as the one of Subent 002, but with a 21193 7 5 better geometric arrangement of the target and the 21193 7 6 manganese bath, resulting in a smaller loss of neutrons21193 7 7 due to leakage at the edge of the manganese bath. 21193 7 8 ERR-ANALYS (DATA-ERR) No information about source of uncertainty 21193 7 9 STATUS (TABLE) Text on p.4 of KFK-454 21193 7 10 HISTORY (19800331A) G.C. Added data set from paris conference. 21193 7 11 (20230130A) SD: SF4=Au-198g -> Au-198 in REACTION code.21193 7 12 BIB updated. 21193 7 13 ENDBIB 11 0 21193 7 14 NOCOMMON 0 0 21193 7 15 DATA 3 1 21193 7 16 EN DATA DATA-ERR 21193 7 17 KEV B B 21193 7 18 30. 0.598 0.012 21193 7 19 ENDDATA 3 0 21193 7 20 ENDSUBENT 19 0 21193 799999 ENDENTRY 7 0 2119399999999