ENTRY 30933 20030124 00003093300000001 SUBENT 30933001 20030124 00003093300100001 BIB 19 69 3093300100002 INSTITUTE (3HUNKOS) First three authors 3093300100003 (3TAICHM) Three last authors 3093300100004 REFERENCE (J,ZP/A,325,69,1986) Detailed paper, with curves 3093300100005 (S,JAERI-M-92-027,9,199203) Table given 3093300100006 (C,86HARROG,1,196,198608) Brief information 3093300100007 AUTHOR (J.CSIKAI,Z.LANTOS,S.SUDAR,T.CHIMOYE,T.VILAITHONG, 3093300100008 N.CHIRAPATPIMOL) 3093300100009 TITLE Study of the excitation functions of Al-27(n,a), 3093300100010 Al-27(n,p) and Si-28(n,p) reactions. 3093300100011 FACILITY (CCW,3HUNKOS) 3093300100012 -Neutron generator at the Institute of Experimental 3093300100013 Physics,Kossuth Univ.,Debrecen; using: 3093300100014 -210 keV analysed d-beam 3093300100015 -Liquid nitrogen-jet cooled TiT target of low-mass 3093300100016 constructions. 3093300100017 -5 mm diam of beam spot 3093300100018 (CCW,3TAICHM) 3093300100019 Measurements were repeated in the range of 3093300100020 13.84-14.70 MeV by J25 neut.generator at Chiang Mai 3093300100021 University,employing : 3093300100022 -a nonanalysed d-beam of 150 keV 3093300100023 -10 mm diam of beam spot 3093300100024 -cold water cooled TiT target of low-mass constructions3093300100025 INC-SOURCE (D-T) 3093300100026 Several neutron emission angles have been used to vary 3093300100027 the neutron energy between 13.5 and 14.8 MeV. 3093300100028 The neutron energy as a function of emission angle has 3093300100029 been determined(both for analysed and nonanalysed 3093300100030 d-beams)using the ratio of the specific activities of 3093300100031 Zr,Au,Ta and Nb foils 3093300100032 SAMPLE Rectangular-shaped al,si samples of 15*10*0.5 mm-3. 3093300100033 METHOD (ACTIV) 3093300100034 DETECTOR (GELI) 3093300100035 (SCIN) NaI(Tl) detector 3093300100036 The energy-efficiency curve of the detectors was 3093300100037 determined by standard g-sources. 3093300100038 PART-DET (DG) 3093300100039 ANALYSIS The measured data were compared with evaluated data 3093300100040 and Hauser-Feshbach model calculation. See figures 3093300100041 in Z.Phys.A. 3093300100042 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) at 14.1 MeV 3093300100043 During the irradiation the total neutron fluence and 3093300100044 the time distribution of neutron yield were measured 3093300100045 by: 3093300100046 * U-238 fission chamber in Debrecen 3093300100047 * NE-213 scintillator in Chiang Mai 3093300100048 * Activation of Al and Nb foils 3093300100049 DECAY-DATA No information given 3093300100050 CORRECTION -The efficiency of the detectors were corrected for: 3093300100051 * Geometry 3093300100052 * Self-absorption 3093300100053 * Energetic beta particles 3093300100054 * Dead time 3093300100055 * Random pile-up 3093300100056 * True coincidence losses 3093300100057 ERR-ANALYS No error analysis given 3093300100058 COMMENT The neutron energy as a function of emission angle 3093300100059 has been determined (both for analysed and nonanalysed 3093300100060 deuteron beams) using the ratio of the specific 3093300100061 activities of Zr,Au,Ta and Nb foils. 3093300100062 FLAG (1.) Data measured at CCW,3HUNKOS. 3093300100063 (2.) Data measured at CCW,3TAICHM. 3093300100064 STATUS Data taken from J,ZP/A,325,pag 70,Table 1., 1987. 3093300100065 HISTORY (19890705C) VOF.- 3093300100066 (19940713U) HW.-Keyword 'FLAG' added in subent 001, 3093300100067 Data flags added in data sections of subents 002-004.- 3093300100068 (19970715U) HW.-Reference corrected.- 3093300100069 (20021106U) OS. Reference added, changed to lower case 3093300100070 and new date format. 3093300100071 ENDBIB 69 0 3093300100072 COMMON 2 3 3093300100073 MONIT EN-NRM 3093300100074 MB MEV 3093300100075 122.0 14.1 3093300100076 ENDCOMMON 3 0 3093300100077 ENDSUBENT 76 0 3093300199999 SUBENT 30933002 20030124 00003093300200001 BIB 3 8 3093300200002 REACTION (13-AL-27(N,A)11-NA-24,,SIG) 3093300200003 METHOD For determination of the relative cross section curve 3093300200004 the Al samples were packed together with Nb sandwich 3093300200005 foils to measure the neutron fluence at different 3093300200006 angles using the flat shape of the Nb-93(n,2n) sigma(e)3093300200007 function. 3093300200008 HISTORY (19940713U) HW.- Data flags added in data section.- 3093300200009 (20011106U) OS. Changed to lower case 3093300200010 ENDBIB 8 0 3093300200011 COMMON 1 3 3093300200012 DATA-ERR 3093300200013 PER-CENT 3093300200014 1.2 3093300200015 ENDCOMMON 3 0 3093300200016 DATA 3 12 3093300200017 EN DATA FLAG 3093300200018 MEV MB NO-DIM 3093300200019 14.83 111.9 1. 3093300200020 14.74 112.2 1. 3093300200021 14.71 113.9 2. 3093300200022 14.62 114.7 2. 3093300200023 14.46 115.6 1. 3093300200024 14.38 118.1 2. 3093300200025 14.07 122.0 2. 3093300200026 14.01 122.0 1. 3093300200027 13.84 122.9 2. 3093300200028 13.74 124.4 1. 3093300200029 13.48 127.1 1. 3093300200030 13.40 126.4 1. 3093300200031 ENDDATA 14 0 3093300200032 ENDSUBENT 31 0 3093300299999 SUBENT 30933003 20030124 00003093300300001 BIB 4 10 3093300300002 REACTION (13-AL-27(N,P)12-MG-27,,SIG) 3093300300003 ERR-ANALYS Total error is about 4% 3093300300004 The errors are due to the following sources: 3093300300005 * Determination of neutron flux 3093300300006 * Counting efficiency 3093300300007 * Counting statistics 3093300300008 COMMENT For a similar experiment at Debrecen with less 3093300300009 accuracy see EXFOR 30640.002 3093300300010 HISTORY (19940713U) HW.- Data flags added in data section.- 3093300300011 (20011106U) OS. Changed to lower case 3093300300012 ENDBIB 10 0 3093300300013 NOCOMMON 0 0 3093300300014 DATA 3 12 3093300300015 EN DATA FLAG 3093300300016 MEV MB NO-DIM 3093300300017 14.83 72.5 1. 3093300300018 14.74 76.0 1. 3093300300019 14.71 75.1 2. 3093300300020 14.62 78.6 2. 3093300300021 14.46 80.2 1. 3093300300022 14.38 75.2 2. 3093300300023 14.07 80.3 2. 3093300300024 14.01 84.0 1. 3093300300025 13.84 85.2 2. 3093300300026 13.74 89.0 1. 3093300300027 13.48 93.0 1. 3093300300028 13.40 91.0 1. 3093300300029 ENDDATA 14 0 3093300300030 ENDSUBENT 29 0 3093300399999 SUBENT 30933004 20030124 00003093300400001 BIB 3 8 3093300400002 REACTION (14-SI-28(N,P)13-AL-28,,SIG) 3093300400003 ERR-ANALYS Total error is about 4% 3093300400004 The errors are due to the following sources: 3093300400005 * Determination of neutron flux 3093300400006 * Counting efficiency 3093300400007 * Counting statistics 3093300400008 HISTORY (19940713U) HW.- Data flags added in data section.- 3093300400009 (20011106U) OS. Changed to lower case 3093300400010 ENDBIB 8 0 3093300400011 NOCOMMON 0 0 3093300400012 DATA 3 12 3093300400013 EN DATA FLAG 3093300400014 MEV MB NO-DIM 3093300400015 14.83 228.0 1. 3093300400016 14.74 239.0 1. 3093300400017 14.71 245.2 2. 3093300400018 14.62 254.0 2. 3093300400019 14.46 255.0 1. 3093300400020 14.38 260.1 2. 3093300400021 14.07 279.1 2. 3093300400022 14.01 270.0 1. 3093300400023 13.84 292.0 2. 3093300400024 13.74 302.0 1. 3093300400025 13.48 315.0 1. 3093300400026 13.40 320.0 1. 3093300400027 ENDDATA 14 0 3093300400028 ENDSUBENT 27 0 3093300499999 ENDENTRY 4 0 3093399999999