ENTRY 32681 20120316 31543268100000001 SUBENT 32681001 20120316 31543268100100001 BIB 16 83 3268100100002 TITLE Cross section measurements for the 143Nd(n,a)140Ce 3268100100003 reaction at 4.0, 5.0 and 6.0 MeV 3268100100004 AUTHOR (Yu.M.Gledenov, M.V.Sedysheva, V.A.Stolupin, 3268100100005 Guohui Zhang, Jiaguo Zhang, Hao Wu, Jiaming Liu, 3268100100006 Jinxiang Chen, G.Khuukhenkhuu, P.E.Koehler, 3268100100007 P.J.Szalanski) 3268100100008 INSTITUTE (4ZZZDUB,3CPRBJG,3MGLNUM,1USAORL,3POLLOU) 3268100100009 REFERENCE (J,PR/C,80,044602,2009) Data given in table 3268100100010 #doi:10.1103/PhysRevC.80.044602 3268100100011 (J,KPS,59,1693,2011) Same data given in table 3268100100012 #doi:10.3938/jkps.59.1693 3268100100013 ((S,ISINN-17,323,2010)=(S,JINR-E3-2010-36,323,2010)) 3268100100014 Preliminary value in table 3268100100015 REL-REF (O,31648002,Guohui Zhang+,J,ARI,67,46,2009) 3268100100016 147Sm(n,a)144Nd data given 3268100100017 (O,32679002,Yu.M.Gledenov+,J,PR/C,82,014601,2010) 3268100100018 149Sm(n,a)146Nd data 3268100100019 FACILITY (VDG,3CPRBJG) 4.5 MV Van de Graaff 3268100100020 SAMPLE (60-ND-143,ENR=0.835) 3268100100021 143Nd(2)O(3) were 4.077 and 3.875 mg/cm2 thick for 3268100100022 forward (0-90 deg) and backward (90-180 deg) alpha 3268100100023 events, respectively, and the diameter of both 3268100100024 samples was 10.8 cm. 3268100100025 The backings of the samples were 0.005 inch thick 3268100100026 aluminum. 3268100100027 DETECTOR (BF3) BF3 long counter as a neutron flux monitor 3268100100028 (IOCH) The twin gridded ionization chamber, 3268100100029 comprised of two symmetric sections with common 3268100100030 cathode. 3268100100031 The outer wall of the chamber was an aluminum 3268100100032 cylinder, 29.0 x 37.0 cm in height and diameter, 3268100100033 with 2.0 mm thick walls. 3268100100034 The cathode, grids, and anodes were rectangular. 3268100100035 The grids consisted of parallel tungsten wires, 3268100100036 coated with gold, which were 0.10 mm in diameter 3268100100037 and spaced 2.0 mm apart. 3268100100038 The effective grid area was 16 x 18 cm2. 3268100100039 Distances from the cathode to grid and from the grid 3268100100040 to anode were 75 and 20 mm, respectively. 3268100100041 A mixture of Kr+2.89% CO2 was used as the working gas 3268100100042 for the ionization chamber. 3268100100043 A gas pressure is 1.90 atm for present measurement. 3268100100044 The high voltages for the cathode, grid and anode 3268100100045 were -3000, 0 and 1500 V, respectively. 3268100100046 (FISCH) Neutron flux determination 3268100100047 MONITOR (92-U-238(N,F),,SIG) 3268100100048 Absolute neutron flux was determined by a small 3268100100049 parallel plate 238U fission chamber. 3268100100050 The abundance of the 238U sample was better than 3268100100051 99.997%. 3268100100052 The mass of the 238U sample was 547.2 +/- 7.1 ug, 3268100100053 the diameter was 2.0 cm. 3268100100054 The working gas fission chamber is flowing Ar+2.85% 3268100100055 CO2 gas at a pressure slightly higher than 1.0 atm. 3268100100056 MONIT-REF (,,3,ENDF/B-VII.0,9237,2006) 3268100100057 INC-SOURCE (D-D) Deuterium gas target were used for production 3268100100058 neutron. 3268100100059 The diameter and the length of the cylindrical gas 3268100100060 cell were 0.9 cm and 2.0 cm, respectively. 3268100100061 The incident window Mo foil is 5.0 um in thickness. 3268100100062 The gas pressure was between 2.9 and 3.1 atm during 3268100100063 experiment. 3268100100064 PART-DET (A) Alphas 3268100100065 CORRECTION The final cross sections were corrected for 3268100100066 attenuation of the neutron flux through the 2 mm 3268100100067 thick aluminum wall of the ionization chamber. 3268100100068 Using the total neutron cross section of aluminum in 3268100100069 ENDF/B-VII.0, this correction factor was calculated 3268100100070 to be 0.971, 0.972 and 0.975 for 4.0, 5.0 and 6.0 MeV 3268100100071 neutrons, respectively. 3268100100072 ERR-ANALYS Uncertainties taken from ISINN-17,p323 (2010) 3268100100073 (ERR-T) The total uncertainty of cross sections (~10%) 3268100100074 (ERR-S,5.,8.5) Number of alpha events Na (5.-8.5%) 3268100100075 (ERR-1) Neutron flux density ratio K (3%) 3268100100076 (ERR-2) Fission counts Nf (2%) 3268100100077 (ERR-3) Atom number of 143Nd (1.5%) 3268100100078 (ERR-4) Atom number of 238U (1.3%) 3268100100079 (MONIT-ERR) 238U fission cross section (1%) 3268100100080 STATUS (TABLE) Table 1 of S,ISINN-17,323,2010 3268100100081 (APRVD) Proof-read by Zhang Guohui (2011-09-04) 3268100100082 HISTORY (20100903C) Compiled by Guochang CHEN; 3268100100083 (20110902A) On. REFERENCE: KPS added 3268100100084 (20120316U) On. REFERENCE: PR/C added 3268100100085 ENDBIB 83 0 3268100100086 COMMON 5 3 3268100100087 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 3268100100088 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3268100100089 3. 2. 1.5 1.3 1. 3268100100090 ENDCOMMON 3 0 3268100100091 ENDSUBENT 90 0 3268100199999 SUBENT 32681002 20110902 31523268100200001 BIB 2 2 3268100200002 REACTION (60-ND-143(N,A)58-CE-140,,SIG) 3268100200003 HISTORY (20110902A) On. ERR-T updated, MONIT from author added 3268100200004 ENDBIB 2 0 3268100200005 NOCOMMON 0 0 3268100200006 DATA 5 3 3268100200007 EN EN-ERR DATA ERR-T MONIT 3268100200008 MEV MEV MB MB MB 3268100200009 4.0 0.23 0.12 0.01 554.40 3268100200010 5.0 0.16 0.21 0.02 546.71 3268100200011 6.0 0.12 0.31 0.03 610.79 3268100200012 ENDDATA 5 0 3268100200013 ENDSUBENT 12 0 3268100299999 ENDENTRY 2 0 3268199999999