ENTRY 30621 20090806 31403062100000001 SUBENT 30621001 20090806 31403062100100001 BIB 13 26 3062100100002 INSTITUTE (3CZRUJF) 3062100100003 (4ZZZDUB) Last author's address. 3062100100004 REFERENCE (J,CZJ/B,32,(1),117,198201) 3062100100005 AUTHOR (J.Cervena,J.Kvitek,J.Vacik,Yu.P.Popov) 3062100100006 TITLE The Nd-143(n,alpha)Ce-140 reaction with 2 keV neutrons 3062100100007 FACILITY (REAC,3CZRUJF) VVR-S reactor. 3062100100008 n-flux =(2.4+-0.4) x 10**6, at 6MW. 3062100100009 INC-SOURCE Filtered beam. Filter of pure metallic scandium. 3062100100010 INC-SPECT Quasi-monoenergetic neutron beam with a mean energy of 3062100100011 2keV and a distribution half-width of 900 eV. 3062100100012 SAMPLE Depositing 19.8 mg of Nd(2)-O(3),(enriched to 83.2% 3062100100013 in Nd-143 isotope), on a 15 micro-m thick Al foil. 3062100100014 METHOD (PHD) The alpha spectrum was accumulated during 3062100100015 590 hours with the filtered neutron beam. 3062100100016 DETECTOR (SOLST) A partially depleted detector with 100 micron 3062100100017 depletion depth and sensitive area of 800 mm2. 3062100100018 MONITOR (3-LI-6(N,T)2-HE-4,,SIG,,,DERIV) =3.23B at 2keV. 3062100100019 The value was obtained by extrapolation of the measured3062100100020 thermal cross-section according to 1/V law. Yu.P.Popov3062100100021 et'al.,Report JINR P3-80-779(1980). 3062100100022 STATUS (APRVD) Approved by author (821027) 3062100100023 (TABLE) Data taken from Czec.J.Phys., 3062100100024 Part B,32,(no.1)(1982)117. 3062100100025 HISTORY (19820326C) KO. 3062100100026 (19820326U) DG.-Corrections in BIB.- 3062100100027 (20090725A) SD:Updated to new date formats,lower case. 3062100100028 ENDBIB 26 0 3062100100029 NOCOMMON 0 0 3062100100030 ENDSUBENT 29 0 3062100199999 SUBENT 30621002 20090806 31403062100200001 BIB 2 7 3062100200002 REACTION (60-ND-143(N,A)58-CE-140,PAR,SIG) 3062100200003 ERR-ANALYS (DATA-ERR) Standard deviation, which combines: 3062100200004 * the statistical uncertainty, 3062100200005 * the uncertainty introduced by the correction 3062100200006 for background and 3062100200007 * possible errors in determination of neutron 3062100200008 flux and number of target nuclei. 3062100200009 ENDBIB 7 0 3062100200010 NOCOMMON 0 0 3062100200011 DATA 5 1 3062100200012 EN-APRX E-LVL DATA DATA-ERR MONIT 3062100200013 KEV MEV MICRO-B MICRO-B B 3062100200014 2.0000E+00 0.0000E+00 3.2000E+01 6.0000E+00 3.2300E+00 3062100200015 ENDDATA 3 0 3062100200016 ENDSUBENT 15 0 3062100299999 ENDENTRY 2 0 3062199999999