ENTRY 31656 20090206 31333165600000001 SUBENT 31656001 20090206 31333165600100001 BIB 14 69 3165600100002 TITLE Thermal neutron cross-section and resonance integral 3165600100003 of the 98Mo(n,gamma)99Mo reaction 3165600100004 AUTHOR (Nguyen Van Do,Pham Duc Khue,Kim Tien Thanh, 3165600100005 Bui Van Loat,Md.S.Rahman,Kyung Sook Kim,Guinyun Kim, 3165600100006 Youngdo Oh,Hee-Seok Lee,Moo-Hyun Cho,In Soo Ko, 3165600100007 Won Namkung) 3165600100008 INSTITUTE (3VN IPH,3KORKNU,3KORPUE) 3165600100009 (3VN VN) College of Natural Sciences, Hanoi National 3165600100010 University, 334 Nguyen Trai, Hanoi, Viet Nam 3165600100011 REFERENCE (J,NIM/B,267,462,2009) 3165600100012 FACILITY (LINAC,3KORPUE) Electron linear accelerator 3165600100013 METHOD (TOF,PSD) the authors also used transmission method 3165600100014 lower-level discriminator 3165600100015 INC-SOURCE (PHOTO) The photo-neutron target was composed of ten 3165600100016 Ta plates with a diameter of 4.9 cm and an effective 3165600100017 thickness of 7.4 cm. There was a 0.15 cm water gap 3165600100018 between Ta plates in order to cool the target 3165600100019 effectively. The housing of the target was made of 3165600100020 titanium. 3165600100021 SAMPLE A high-purity (>99.99%) Mo foil with a natural isotopic3165600100022 composition (92Mo 14.84%, 94Mo 9.25%, 95Mo 15.92%, 3165600100023 96Mo 16.68%, 97Mo 9.55%, 98Mo 24.13%, and 100Mo 9.63%) 3165600100024 was used for measuring the thermal neutron cross-sect. 3165600100025 and the resonance integral of the 98Mo(n,gamma)99Mo 3165600100026 reaction. 3165600100027 Natural Mo metallic foils were 12.7 mm in diameter and 3165600100028 0.1 mm in thickness. The Au and In metallic foils were 3165600100029 used as the comparator reactions and the neutron flux 3165600100030 monitors, respectively. 3165600100031 Characteristics of Mo, Au and In foils: 3165600100032 Foil Diam.(mm) Thick.(mm) Weight (g) Purity (%)3165600100033 Au 1 12.7 0.03 0.0731+-0.0004 99.95 3165600100034 Au 2 12.7 0.03 0.0726+-0.0004 99.95 3165600100035 Mo 2 12.7 0.10 0.1284+-0.0006 99.90 3165600100036 Mo 3 12.7 0.10 0.1290+-0.0006 99.90 3165600100037 In 11 12.7 0.05 0.0470+-0.0004 99.99 3165600100038 In 12 12.7 0.05 0.0466+-0.0004 99.99 3165600100039 In 13 12.7 0.05 0.0471+-0.0004 99.99 3165600100040 In 14 12.7 0.05 0.0468+-0.0004 99.99 3165600100041 In 15 12.7 0.05 0.0472+-0.0004 99.99 3165600100042 In 16 12.7 0.05 0.0471+-0.0004 99.99 3165600100043 DECAY-DATA (42-MO-99,2.7489D,DG,140.511,0.0452, 3165600100044 DG,158.782,0.00189, 3165600100045 DG,181.068,0.0599, 3165600100046 DG,580.51,0.0032, 3165600100047 DG,739.500,0.1213, 3165600100048 DG,777.921,0.0426) 3165600100049 MONITOR (49-IN-115(N,G)49-IN-116-M,,SIG) 3165600100050 (13-AL-27(N,A)11-NA-24,,SIG) The fast neutron flux was 3165600100051 also checked based on the well known reaction.) 3165600100052 DECAY-MON (49-IN-116-M,54.41MIN,DG,416.86,0.277, 3165600100053 DG,1097.3,0.562, 3165600100054 DG,1293.54,0.844) 3165600100055 (11-NA-24,14.9590HR,DG,1368.633,1.00, 3165600100056 DG,2754.028,0.9994) 3165600100057 The main nuclear data together with their uncertainties3165600100058 for the nuclear reactions based on the table of 3165600100059 isotopes: NuDat2, The NuDat Program for Nuclear Data 3165600100060 on the Web, National Nuclear Center, Brookhaven 3165600100061 National Laboratory, Version 2.4, 2007. 3165600100062 . 3165600100063 DETECTOR (HPGE) The gamma-ray spectrometer was a p-type 3165600100064 coaxial CANBERRA high-purity germanium (HPGe)-detector 3165600100065 with a diameter of 59.2 mm and a thickness of 30 mm. 3165600100066 The HPGe-detector was coupled to a computer- based 3165600100067 multichannel analyzer with the associated electronics 3165600100068 to determine the photopeak area of gamma-ray spectrum.3165600100069 STATUS (TABLE) Data from the tables of the article 3165600100070 HISTORY (20090206C) SD 3165600100071 ENDBIB 69 0 3165600100072 NOCOMMON 0 0 3165600100073 ENDSUBENT 72 0 3165600199999 SUBENT 31656002 20090206 31333165600200001 BIB 5 10 3165600200002 REACTION (42-MO-98(N,G)42-MO-99,,SIG) tbl.6 3165600200003 MONITOR (79-AU-197(N,G)79-AU-198,,SIG,,MXW) 3165600200004 MONIT-REF (22842002,M.Karadag,J,ANE,31,1285,2004) 3165600200005 DECAY-MON (79-AU-198,2.69517D,DG,411.80205,0.9558, 3165600200006 DG,675.8836,0.0084) 3165600200007 ERR-ANALYS (ERR-T) the main sources of the uncertainties for the 3165600200008 thermal neutron cross-section measurement are due to: 3165600200009 (ERR-S) the statistical error, 3165600200010 (ERR-1) the detection efficiency and 3165600200011 (ERR-2) the gamma-ray intensity. 3165600200012 ENDBIB 10 0 3165600200013 COMMON 3 3 3165600200014 ERR-1 ERR-2 ERR-S 3165600200015 PER-CENT PER-CENT PER-CENT 3165600200016 2.5 2.75 1.8 3165600200017 ENDCOMMON 3 0 3165600200018 DATA 5 1 3165600200019 EN-DUMMY DATA ERR-T MONIT MONIT-ERR 3165600200020 EV B B B B 3165600200021 0.0253 0.136 0.007 98.65 0.09 3165600200022 ENDDATA 3 0 3165600200023 ENDSUBENT 22 0 3165600299999 SUBENT 31656003 20090206 31333165600300001 BIB 4 9 3165600300002 REACTION (42-MO-98(N,G)42-MO-99,,RI) tbl.6 3165600300003 MONITOR (79-AU-197(N,G)79-AU-198,,RI) 3165600300004 MONIT-REF (22842003,M.Karadag,J,ANE,31,1285,2004) 3165600300005 ERR-ANALYS (ERR-T) The main sources of the uncertainties for the 3165600300006 resonance integral measurement are due to: 3165600300007 (ERR-1) the reference thermal neutron cross-section, 3165600300008 (ERR-2) the alpha-shape factor, 3165600300009 (ERR-3) the cadmium ratio, and 3165600300010 (ERR-4) the epithermal neutron self-shielding factor. 3165600300011 ENDBIB 9 0 3165600300012 COMMON 4 3 3165600300013 ERR-1 ERR-2 ERR-3 ERR-4 3165600300014 PER-CENT PER-CENT PER-CENT PER-CENT 3165600300015 4.61 4.5 2.18 1.35 3165600300016 ENDCOMMON 3 0 3165600300017 DATA 5 1 3165600300018 EN-MIN DATA ERR-T MONIT MONIT-ERR 3165600300019 EV B B B B 3165600300020 0.55 7.02 0.62 1550. 28. 3165600300021 ENDDATA 3 0 3165600300022 ENDSUBENT 21 0 3165600399999 ENDENTRY 3 0 3165699999999