ENTRY 23154 20111202 22312315400000001 SUBENT 23154001 20111202 22312315400100001 BIB 19 89 2315400100002 TITLE Isomeric cross section of the 197Au(n,2n) reaction 2315400100003 AUTHOR (A.Tsinganis,M.Diakaki,M.Kokkoris,A.Lagoyannis, 2315400100004 E.Mara,C.T.Papadopoulos,R.Vlastou) 2315400100005 INSTITUTE (2GRCTUA) Department of Physics, National Technical 2315400100006 University of Athens, Athens, Greece. A.Tsinganis, 2315400100007 M.Diakaki, M.Kokkoris, E.Mara, C.T.Papadopoulos, 2315400100008 R.Vlastou 2315400100009 (2GRCATH) Institute of Nuclear Physics, National 2315400100010 Centre of Scientific Research (NCSR) "Demokritos", 2315400100011 Athens, Greece. A.Lagoyannis, 2315400100012 REFERENCE (J,PR/C,83,024609,2011) Main reference, data are given 2315400100013 #doi:10.1103/PhysRevC.83.024609 2315400100014 FACILITY (VDGT,2GRCATH) 2315400100015 INC-SOURCE (D-D) The quasimonoenergetic neutron beam was produced 2315400100016 via the 2H(d,n)3He reaction by bombarding a deuterium 2315400100017 gas target with a deuteron beam at currents aprx 1-2 2315400100018 mu-A. Neutron flux varied between 3.E+05 and 2315400100019 4.E+06 n/(cm2 s) in the four runs performed. 2315400100020 SAMPLE (79-AU-197,ENR=0.9999) High-purity natural gold foils 2315400100021 <99.99% 197Au> with a diameter of 14 mm and thickness 2315400100022 of 0.5 mm were used. Two Al foils of the same 2315400100023 diameter and thickness were placed immediately before 2315400100024 and after the gold foil and were used to determine 2315400100025 the neutron flux. 2315400100026 METHOD (ACTIV,STTA) Four irradiations have been carried out. 2315400100027 The SULSA unfolding code was used. 2315400100028 MONITOR (13-AL-27(N,A)11-NA-24,,SIG,,,EVAL) 2315400100029 The integrated neutron flux was determined by using 2315400100030 the cross-section values for the 27Al(n,alpha)24Na 2315400100031 reaction found in literature (see MONIT-REF) and by 2315400100032 averaging over the deduced values in the front 2315400100033 and back Al foils. 2315400100034 DECAY-MON (11-NA-24,14.9590HR,DG,1368.6,1.) 2315400100035 MONIT-REF (,A.Carlson+,J,NDS,107,2931,2006) 2315400100036 DETECTOR (HPGE) The induced activity on the samples was measured2315400100037 with a 56% relative efficiency high-purity germanium 2315400100038 (HPGe) detector. The detector was calibrated with 2315400100039 152Eu and 207Bi sources. 2315400100040 (BF3) Beam fluctuations were monitored with a BF3 2315400100041 counter placed at a distance of 3 m from the 2315400100042 deuterium gas target. 2315400100043 ANALYSIS .The STAPRE-F code was used for estimation 2315400100044 energy-averaged cross sections for particle-induced 2315400100045 reactions with several possible emitted particles. 2315400100046 The neutron transmission coefficients were calculated 2315400100047 using the ECIS03 code with the global optical model 2315400100048 parameters by Koning and Delaroche. 2315400100049 The energies, spins, parities, and branching ratios of2315400100050 the discrete levels for each nucleus involved were 2315400100051 taken from Nuclear Data Sheets (see REL-REF), and the 2315400100052 first 90 levels of 196Au were included (up to 2315400100053 ~0.730 MeV). For the levels with unknown spin and 2315400100054 parity, estimates from neighboring levels were made, 2315400100055 while for levels with more than one spin assignment, a2315400100056 choice was made in order to include a variety of 2315400100057 spin values. 2315400100058 REL-REF (M,,J.Raynal,R,CEA-N-2772,1994) - ECIS03 code 2315400100059 (M,,A.J.Koning+,J,NP/A,713,231,2003) - Global optical 2315400100060 model parameters 2315400100061 (N,,H.Xiaolong,J,NDS,108,1093,2007) - The energies, 2315400100062 spins, parities, and branching ratios were used. 2315400100063 ADD-RES (THEO,COMP) Theoretical calculations of the above cross2315400100064 sections in the 8-25 MeV region were carried out 2315400100065 with the use of the STAPRE-F, EMPIRE,and TALYS codes,2315400100066 which were also compared in their implementation of 2315400100067 the generalized superfluid model. 2315400100068 ERR-ANALYS (ERR-T) Total uncertainties are quadratic sum of: 2315400100069 (EN-ERR,,1.) Error of the neutron energy < 1% 2315400100070 (ERR-1,4.,6.5) Error of the neutron flux 4 - 6.5%, 2315400100071 including 2% uncertainty in the 27Al(n,alpha)24Na 2315400100072 cross section 2315400100073 (ERR-2) Error due to correction factors 2% 2315400100074 (ERR-3,,0.5) Error due to time factors <0.5% 2315400100075 (ERR-4) Error of the gamma-ray intensity per decay 2315400100076 1.1%/0.2% 2315400100077 (ERR-5) Detector efficiency 5%, 2315400100078 including ERR-S given in Subents. 2315400100079 (MONIT-ERR) 2% uncertainty in the 27Al(n,alpha)24Na 2315400100080 cross section 2315400100081 .The value of the counting statistics uncertainty 2315400100082 is 41.5% for the 9.5-MeV run, owing to the low beam 2315400100083 current and shorter than desired irradiation, leading 2315400100084 to a total cross-section uncertainty of 42.4%. 2315400100085 CORRECTION Corrections were made for: 2315400100086 * contribution of background 'parasitic' neutrons; 2315400100087 * self-absorption effects 2315400100088 * target geometry 2315400100089 STATUS (TABLE) Data from Table VI of PR/C,83,024609,2011 2315400100090 HISTORY (20111202C) SM 2315400100091 ENDBIB 89 0 2315400100092 COMMON 3 3 2315400100093 ERR-2 ERR-5 MONIT-ERR 2315400100094 PER-CENT PER-CENT PER-CENT 2315400100095 2. 5. 2. 2315400100096 ENDCOMMON 3 0 2315400100097 ENDSUBENT 96 0 2315400199999 SUBENT 23154002 20111202 22312315400200001 BIB 4 9 2315400200002 REACTION (79-AU-197(N,2N)79-AU-196-G+M1,,SIG) 2315400200003 REL-REF (A,10536001,B.P.Bayhurst+,J,PR/C,12,451,1975) 2315400200004 (D,11504001,H.A.Tewes+,W,Tewes,1960) 2315400200005 Tech. Rep. 6028, 1960 (unpublished) 2315400200006 data retrieved from EXFOR 2315400200007 DECAY-DATA (79-AU-196-G,6.1669D,DG,333.0,0.229, 2315400200008 DG,355.7,0.87, 2315400200009 DG,426.1,0.066) 2315400200010 ERR-ANALYS (ERR-S,0.2,1.2) Counting statistics 0.2-1.2% 2315400200011 ENDBIB 9 0 2315400200012 COMMON 1 3 2315400200013 ERR-4 2315400200014 PER-CENT 2315400200015 1.1 2315400200016 ENDCOMMON 3 0 2315400200017 DATA 3 4 2315400200018 EN DATA ERR-T 2315400200019 MEV MB MB 2315400200020 9.0 328. 26. 2315400200021 9.5 695. 60. 2315400200022 10.0 1052. 73. 2315400200023 10.5 1404. 102. 2315400200024 ENDDATA 6 0 2315400200025 ENDSUBENT 24 0 2315400299999 SUBENT 23154003 20111202 22312315400300001 BIB 3 4 2315400300002 REACTION (79-AU-197(N,2N)79-AU-196-M2,,SIG) 2315400300003 DECAY-DATA (79-AU-196-M2,9.6HR,DG,147.8,0.435, 2315400300004 DG,188.3,0.300) 2315400300005 ERR-ANALYS (ERR-S,4.2,15.1) Counting statistics 4.2-15.1% 2315400300006 ENDBIB 4 0 2315400300007 COMMON 1 3 2315400300008 ERR-4 2315400300009 PER-CENT 2315400300010 0.2 2315400300011 ENDCOMMON 3 0 2315400300012 DATA 3 4 2315400300013 EN DATA ERR-T 2315400300014 MEV MB MB 2315400300015 9.0 0.8 0.1 2315400300016 9.5 8.9 3.8 2315400300017 10.0 16.2 1.6 2315400300018 10.5 32.8 2.7 2315400300019 ENDDATA 6 0 2315400300020 ENDSUBENT 19 0 2315400399999 SUBENT 23154004 20111202 22312315400400001 BIB 3 8 2315400400002 REACTION (79-AU-197(N,2N)79-AU-196-M1/M2,,SIG/RAT) 2315400400003 DECAY-DATA (79-AU-196-G,6.1669D,DG,333.0,0.229, 2315400400004 DG,355.7,0.87, 2315400400005 DG,426.1,0.066) 2315400400006 (79-AU-196-M2,9.6HR,DG,147.8,0.435, 2315400400007 DG,188.3,0.300) 2315400400008 STATUS (DEP,23154002) 2315400400009 (DEP,23154003) 2315400400010 ENDBIB 8 0 2315400400011 NOCOMMON 0 0 2315400400012 DATA 3 4 2315400400013 EN DATA ERR-T 2315400400014 MEV NO-DIM NO-DIM 2315400400015 9.0 0.0024 0.0003 2315400400016 9.5 0.013 0.006 2315400400017 10.0 0.015 0.002 2315400400018 10.5 0.023 0.003 2315400400019 ENDDATA 6 0 2315400400020 ENDSUBENT 19 0 2315400499999 ENDENTRY 4 0 2315499999999