ENTRY 31696 20110816 31513169600000001 SUBENT 31696001 20110816 31513169600100001 BIB 16 76 3169600100002 TITLE An Am/Be neutron source and its use in integral tests 3169600100003 of differential neutron reaction cross-section data 3169600100004 AUTHOR (M.S.Uddin, M.R.Zaman, S.M.Hossain, I.Spahn, S.Sudar, 3169600100005 S.M.Qaim) 3169600100006 INSTITUTE (3BANRAJ,3BANRAM,2GERJUL,3HUNKOS) 3169600100007 REFERENCE (J,ARI,68,1656,2010) 3169600100008 FACILITY (NGEN,3BANRAJ) 3169600100009 INC-SOURCE (AM-BE) The Am/Be neutron source from the Department 3169600100010 of Applied Chemistry and Chemical Technology of the 3169600100011 Rajshahi University. The active component (A) 3169600100012 consists of the alpha-emitting radionuclide 241Am 3169600100013 (activity 111 GBq in 1977) alloyed with Be,and sealed 3169600100014 in a cylindrical metal capsule which was then 3169600100015 covered by a graphite layer to avoid any leak of the 3169600100016 activity 3169600100017 Considering the distance and the solid angle subtended 3169600100018 by a sample at two positions, the flux density at that 3169600100019 position was estimated to be 1.5 x 10**5 n/cm2/s. 3169600100020 SAMPLE High-purity foils of several metals were cut in 3169600100021 circular discs (dia. 2 cm) and irradiated either 3169600100022 individually or together in a stack. The choice of a 3169600100023 foil depended on the nuclear reaction induced in it. 3169600100024 The foils covered three energy regions of the neutron 3169600100025 spectrum, viz. thermal, low-energy(<1.5 MeV)and high 3169600100026 energy (>1.5 MeV). Several stacks of Fe, Co, Ni and Mo3169600100027 foils were prepared and irradiated in various positions3169600100028 The duration of each irradiation was about 300h. 3169600100029 Au and In foils, on the other hand, were irradiated 3169600100030 individually, each for about 24h, without placing the 3169600100031 active component in the paraffin shielding. 3169600100032 METHOD (ACTIV,STTA,SITA) The neutron activation through 3169600100033 usage spectrum average technique 3169600100034 MONITOR ((MONIT1)49-IN-113(N,G)49-IN-114-M,,SIG) 3169600100035 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 3169600100036 Both reactions are used for monitor 3169600100037 thermal neutron flux 3169600100038 ((MONIT3)49-IN-115(N,INL)49-IN-115-M,,SIG) used for 3169600100039 monitor neutron flux for En > 0.37 MeV 3169600100040 ((MONIT4)28-NI-58(N,P)27-CO-58,,SIG) used for monitor 3169600100041 neutron flux for En > 1.5 MeV 3169600100042 DECAY-MON ((MONIT1)49-IN-114-M,49.5D,DG,192.,0.1556) 3169600100043 ((MONIT2)79-AU-198,2.69D,DG,411.8,0.96) 3169600100044 ((MONIT3)49-IN-115-M,4.49HR,DG,336.2,0.4583) 3169600100045 ((MONIT4)27-CO-58,70.86D,DG,811.,0.99) 3169600100046 DETECTOR (HPGE) A high-purity germanium(HPGe) gamma-ray 3169600100047 detector associated with a digital gamma 3169600100048 spectrometry system (ORTECDSPEC TM) and Maestro data 3169600100049 acquisition software was used to measure radioactivity.3169600100050 Radioactivity of the 115mIn and 198Au were measured 3169600100051 nondestructively at the Institute of Nuclear Science 3169600100052 and Technology(INST), Savar, Dhaka, Bangladesh. 3169600100053 The radioactivities of the relatively long-lived 3169600100054 radionuclides 54Mn, 59Fe, 58Co, 92mNb and 114mIn were 3169600100055 measured using a low level HPGe gamma-ray detector 3169600100056 at the Institute fur Nuklearchemie, Forschungszentrum 3169600100057 Julich, Germany. 3169600100058 The efficiency versus energy curve of the HPGe 3169600100059 gamma-ray detector was determined using the standard 3169600100060 point sources 22Na, 57Co, 60Co, 133Ba, 137Cs, 152Eu 3169600100061 and 226Ra. 3169600100062 PART-DET (DG) 3169600100063 MISC-COL (MISC) Reaction threshold 3169600100064 ERR-ANALYS (ERR-T) The main sources of uncertainties in the 3169600100065 measured integral cross sections are: 3169600100066 (ERR-S,1.,7.) statistical error 1-7% 3169600100067 (MONIT-ERR) Uncertainty of monitor cross-section 3169600100068 (ERR-1) Detector efficiency uncertainty 3169600100069 (ERR-2) Mass uncertainty 3169600100070 (ERR-3) Uncertainty in peak area analysis 3169600100071 (ERR-4,0.,3.) Uncertainty in coincidence loss 3169600100072 (ERR-5,,0.1) Uncertainty in half-life of product 3169600100073 (ERR-6,,0.2) Uncertainty in gamma-ray intensity 3169600100074 STATUS (TABLE) Data from Tbl.4 of ARI,68,1656,2010 3169600100075 HISTORY (20100609C) SD 3169600100076 (20110509A) On. INC-SOURCE corrected 3169600100077 (20110816A) On. MONIT3, ERR-ANALYS corrected. 3169600100078 ENDBIB 76 0 3169600100079 COMMON 7 6 3169600100080 ERR-1 ERR-2 ERR-3 MONIT3 MONIT3-ERR MONIT4 3169600100081 MONIT4-ERR 3169600100082 PER-CENT PER-CENT PER-CENT MB MB MB 3169600100083 MB 3169600100084 5.0 0.01 2. 201. 8. 391. 3169600100085 19. 3169600100086 ENDCOMMON 6 0 3169600100087 ENDSUBENT 86 0 3169600199999 SUBENT 31696002 20100609 31463169600200001 BIB 2 2 3169600200002 REACTION (26-FE-54(N,P)25-MN-54,,SIG,,SPA) 3169600200003 DECAY-DATA (25-MN-54,312.2D,DG,834.9,0.9998) 3169600200004 ENDBIB 2 0 3169600200005 NOCOMMON 0 0 3169600200006 DATA 4 1 3169600200007 EN-MIN DATA ERR-T MISC 3169600200008 MEV MB MB MEV 3169600200009 1.5 311. 26. 1.75 3169600200010 ENDDATA 3 0 3169600200011 ENDSUBENT 10 0 3169600299999 SUBENT 31696003 20100609 31463169600300001 BIB 2 2 3169600300002 REACTION (27-CO-59(N,P)26-FE-59,,SIG,,SPA) 3169600300003 DECAY-DATA (26-FE-59,44.50D,DG,1099.2,0.565) 3169600300004 ENDBIB 2 0 3169600300005 NOCOMMON 0 0 3169600300006 DATA 4 1 3169600300007 EN-MIN DATA ERR-T MISC 3169600300008 MEV MB MB MEV 3169600300009 1.5 9.3 1.0 2.50 3169600300010 ENDDATA 3 0 3169600300011 ENDSUBENT 10 0 3169600399999 SUBENT 31696004 20100609 31463169600400001 BIB 2 2 3169600400002 REACTION (42-MO-92(N,P)41-NB-92-M,,SIG,,SPA) 3169600400003 DECAY-DATA (41-NB-92-M,10.15D,DG,934.5,0.990) 3169600400004 ENDBIB 2 0 3169600400005 NOCOMMON 0 0 3169600400006 DATA 4 1 3169600400007 EN-MIN DATA ERR-T MISC 3169600400008 MEV MB MB MEV 3169600400009 1.5 45. 4.6 2.25 3169600400010 ENDDATA 3 0 3169600400011 ENDSUBENT 10 0 3169600499999 ENDENTRY 4 0 3169699999999