ENTRY 30614 20090805 31403061400000001 SUBENT 30614001 20090805 31403061400100001 BIB 18 46 3061400100002 TITLE Excitation curve measurement for the reaction 3061400100003 Y-89(n,2n)Y-88. 3061400100004 AUTHOR (Huang Jianzhou,Lu HanlLin,Li Jizhou,Fan Peiguo) 3061400100005 INSTITUTE (3CPRAEP) 3061400100006 EXP-YEAR (1980) 3061400100007 REFERENCE (J,CNP,2,(3),213,1980) in Chinese, English abstract 3061400100008 (R,INDC(CPR)-16,1989) Data slightly revised,exp.summary3061400100009 (difference is insignificant) 3061400100010 SAMPLE Powder sample of Y(2)-O(3). 99.9% purity. 3061400100011 Compressed disk of diam. 11 mm 3061400100012 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) at 14.58+-0.21 MeV. 3061400100013 MONIT-REF (30523002,ZHAO WENRONG,R,INDC(CPR)-16,198908) 3061400100014 FACILITY (CCW,3CPRAEP) For E(n)=14.58 MeV. 3061400100015 (VDG,3CPRAEP) 3061400100016 INC-SOURCE (D-T) Ti-T target. 3061400100017 .About 0.5 to 0.6 mg/cm2 thickness for Cockcroft-Walton3061400100018 accelerator, (E(d)= 200 keV) 3061400100019 .About 0.224 mg/cm2 thickness and E(d)=200keV for Van 3061400100020 de Graaff accelerator. (Producing neutron between 3061400100021 (3.51 to 14.96 MeV). 3061400100022 .About 2 mg/cm2 thickness and E(d)= average 1.5 and 3061400100023 2 MeV for Van de Graaff. (Producing neutron with energy3061400100024 between 12.8 and 18 MeV.) 3061400100025 METHOD (ACTIV) Recoil alpha particle method was used for the 3061400100026 Cockcroft Walton accelerat. to monitor the neutron-flux3061400100027 DETECTOR (NAICR) 10 cm dia. and 7.6 cm long NaI(Tl) scintillator3061400100028 PART-DET (DG) 3061400100029 DECAY-DATA (39-Y-88-G,106.6D,DG,898.,0.927) 3061400100030 CORRECTION After considering the effect of the oxide layer at the 3061400100031 surface of t-Ti target ,the neutron energy was modified3061400100032 from 14.61 to 14.58 MeV. 3061400100033 COMMENT .0.91 eV gamma from Y-89(n,p)Sr-89 is negligible, 3061400100034 because the low cross-section(about 25mb) and the low 3061400100035 abundance(0.01%) of the decay gamma. 3061400100036 .The decay gamma(1.07 MeV) from Rb-86(TC1/2)=18.66 day)3061400100037 of Y-89(n,a)Rb-86 with the cross-section of 5 mb gives3061400100038 the 0.2% influence to the result after 10 days' 3061400100039 irradiation. 3061400100040 In the INDC(CPR)-16 report all of the early data were 3061400100041 adjusted for the new geometry and neutron energy 3061400100042 STATUS (TABLE) Data taken from INDC(CPR)-16 report, p.41 3061400100043 HISTORY (19811231C) KO. 3061400100044 (19850215U) OS. Country code corrected. 3061400100045 (19900905A) VOF.-Data values slightly corrected + small3061400100046 updates in bib section 3061400100047 (20090725A) SD:Updated to new date formats,lower case. 3061400100048 ENDBIB 46 0 3061400100049 COMMON 4 3 3061400100050 EN-NRM EN-RSL MONIT MONIT-ERR 3061400100051 MEV MEV MB MB 3061400100052 14.58 0.21 115.8 3.0 3061400100053 ENDCOMMON 3 0 3061400100054 ENDSUBENT 53 0 3061400199999 SUBENT 30614002 20090805 31403061400200001 BIB 4 24 3061400200002 REACTION (39-Y-89(N,2N)39-Y-88,,SIG) 3061400200003 ERR-ANALYS (ERR-T) at 14.61 MeV, the error of 4% consists of 3061400200004 the following, (normalization energy to the monitor) 3061400200005 .Monitor X-section +- 2.5 3061400200006 .Det.eff.at full energy 3061400200007 peak of gamma +- 2.5 3061400200008 .Gain shift of photomultiplier +- 1 3061400200009 .Self-absorp.correction +- 0.4 3061400200010 .Stand deviation +- 1.5 3061400200011 .Sample weighing error +- 0.1 (all in %) 3061400200012 Total +- 4%. 3061400200013 .For the rest energies, 3061400200014 the error of relative measurement,including neutron 3061400200015 ang.divergences(+-3% for VDG, +-1% for Cockcroft), 3061400200016 and statistical error, is given. 3061400200017 FLAG (1.) Normalization energy to the monitor reaction. 3061400200018 ANALYSIS From all experimental results of Y-89(n,2n)Y-88 until 3061400200019 1980, the authors issued a recommended curve in the 3061400200020 neutron energy range between 12 and 28 MeV, as follows3061400200021 sigma(mb) = 1.018 * (1236 + 48.99*E' - 185.0*E'**2 3061400200022 + 68.73*E'**3 - 23.39*E'**4 3061400200023 - 7.033*E'**5), 3061400200024 where 3061400200025 E' = -12.95+10.33*log(E(n)). E(n)=neutron energy.3061400200026 ENDBIB 24 0 3061400200027 NOCOMMON 0 0 3061400200028 DATA 5 13 3061400200029 EN EN-RSL DATA ERR-T FLAG 3061400200030 MEV MEV MB MB NO-DIM 3061400200031 12.81 0.13 381. 22. 3061400200032 13.51 0.16 702. 30. 3061400200033 13.65 0.20 746. 40. 3061400200034 13.69 0.22 755. 41. 3061400200035 14.09 0.07 899. 39. 3061400200036 14.61 0.21 1018. 34. 1. 3061400200037 14.70 0.23 1048. 52. 3061400200038 14.96 0.06 1076. 48. 3061400200039 15.68 0.31 1156. 60. 3061400200040 16.08 0.33 1204. 62. 3061400200041 16.63 0.30 1257. 64. 3061400200042 17.20 0.28 1270. 68. 3061400200043 18.00 0.30 1287. 66. 3061400200044 ENDDATA 15 0 3061400200045 ENDSUBENT 44 0 3061400299999 ENDENTRY 2 0 3061499999999