ENTRY 41508 20150627 41694150800000001 SUBENT 41508001 20150627 41694150800100001 BIB 14 33 4150800100002 TITLE Relative yield of delayed neutrons and half-life of 4150800100003 their precursor nuclei with fissioning of Pu-239 by 4150800100004 14.2-17.9 MeV neutrons . 4150800100005 AUTHOR (V.A.Roschenko, V.M.Piksaikin, L.E.Kazakov,G.G.Korolev)4150800100006 INSTITUTE (4RUSFEI) 4150800100007 REFERENCE (J,AE,101,(6),441,200612) Main Reference 4150800100008 (J,AE/T,101,(6),897,2006) Engl. transl. of J,AE,101 . 4150800100009 #doi:10.1007/s10512-006-0188-z 4150800100010 REL-REF (N,,V.M.Piksaikin+,J,PNE,41,(1-4),203,2002) 4150800100011 (N,,V.M.Piksaikin+,J,AE,85,(1),51,1998) 4150800100012 Experiment details. 4150800100013 FACILITY (VDG) Cascade generator CG-2.5 4150800100014 METHOD (ACTIV) Cyclic radiation . 37 cycles. 4150800100015 INC-SOURCE (D-T) Solid tritium target on molybdenum or copper 4150800100016 backing with titanium layer of 1 mg/cm**2. 4150800100017 Deuteron energy 0.5 - 2. MeV . 4150800100018 INC-SPECT Produced neutron at angles 0 and 90 degrees to 4150800100019 deuteron beam. Neutron energy range 14.2 - 17.9 MeV. 4150800100020 DETECTOR (LONGC) Long counter and fission chamber for neutron 4150800100021 (FISCH) beam monitoring. 4150800100022 (D4PI) 4PI detector for delayed neutrons registration.4150800100023 SAMPLE Pu-239 sample of 2.61 g mass as 6 metallic discs of 4150800100024 about 1 mm thickness and 5.6 mm diameter. 4150800100025 ANALYSIS 6-group presentation and iterative method of least 4150800100026 squares were used in data analysis. 4150800100027 COMMENT Work was Made by Support of Russian Fond of 4150800100028 Bound Researches and Administration of Kaluga Region 4150800100029 #05-02-08044. 4150800100030 HISTORY (20080411C) Compiled at CJD. M.M. 4150800100031 (20110623U) Engl. translation of J,AE was added. 4150800100032 (20150513A) V.Z. COVARIANCE lines were corrected 4150800100033 according to new format. 4150800100034 (20150627U) M.M. Cosmetic correction. 4150800100035 ENDBIB 33 0 4150800100036 NOCOMMON 0 0 4150800100037 ENDSUBENT 36 0 4150800199999 SUBENT 41508002 20150627 41694150800200001 BIB 4 42 4150800200002 REACTION ((94-PU-239(N,F),DL/GRP,NU)/(94-PU-239(N,F),DL,NU)) 4150800200003 6-Group Delayed Neutron Abundances 4150800200004 ERR-ANALYS (DATA-ERR) Errors are not specified 4150800200005 EN-RSL - error of EN, assigned as energy resolution 4150800200006 according to author's oral comment. 4150800200007 COVARIANCE Correlated parameters 4150800200008 ai - relative yield, 4150800200009 Ti - HL of delayed neutrons precursors, 4150800200010 i - group number. 4150800200011 (XY,12,N,Correlated Parameters) 4150800200012 N Parameter 4150800200013 1 a1 4150800200014 2 T1 4150800200015 3 a2 4150800200016 4 T2 4150800200017 5 a3 4150800200018 6 T3 4150800200019 7 a4 4150800200020 8 T4 4150800200021 9 a5 4150800200022 10 T5 4150800200023 11 a6 4150800200024 12 T6 4150800200025 Correlation matrix: 4150800200026 (Z,78,NO-DIM,COR) 4150800200027 1. 4150800200028 -0 1. 4150800200029 0. 0. 1. 4150800200030 -.18 -.52 0. 1. 4150800200031 0. 0.26 0.41 0.33 1. 4150800200032 0. -.13 -.16 0.65 -.22 1. 4150800200033 0. 0.43 0.6 0.45 -.07 0.51 1. 4150800200034 0. 0.08 0.14 0.01 -.46 0. 0.12 1. 4150800200035 0. 0.08 0.11 0.06 0.02 0.03 -.05 0.19 1. 4150800200036 0. 0.04 0.06 0.05 0.01 0.05 -.07 0.09 0. 1. 4150800200037 0. 0.01 0.02 0.01 0. 0. 0. 0.03 -.01 0. 1. 4150800200038 0. 0.01 0.02 0.01 0. 0. 0. 0.04 -.01 0. 0. 1. 4150800200039 Comment of compiler M.M.: Correlation matrix is given 4150800200040 in Table 2 of J,AE,101,(6),441,2006; 4150800200041 correlation between T1 and a1 in this Table 2 is "-", 4150800200042 value "0." instead of "-" is used in this Subent . 4150800200043 STATUS (TABLE) Table 1 of J,AE,101,(6),441,2006. 4150800200044 ENDBIB 42 0 4150800200045 COMMON 1 3 4150800200046 EN-RSL 4150800200047 MEV 4150800200048 0.2 4150800200049 ENDCOMMON 3 0 4150800200050 DATA 5 18 4150800200051 EN HL HL-ERR DATA DATA-ERR 4150800200052 MEV SEC SEC NO-DIM NO-DIM 4150800200053 15.8 55.76 0.69 0.054 0.001 4150800200054 15.8 20.97 0.27 0.1857 0.004 4150800200055 15.8 4.75 0.09 0.241 0.006 4150800200056 15.8 2.13 0.05 0.362 0.008 4150800200057 15.8 0.56 0.02 0.118 0.003 4150800200058 15.8 0.215 0.006 0.039 0.001 4150800200059 16.8 55.44 0.73 0.056 0.001 4150800200060 16.8 20.53 0.26 0.203 0.005 4150800200061 16.8 4.68 0.09 0.234 0.006 4150800200062 16.8 2.17 0.05 0.348 0.008 4150800200063 16.8 0.55 0.02 0.119 0.004 4150800200064 16.8 0.215 0.006 0.039 0.001 4150800200065 17.9 51.62 0.72 0.056 0.001 4150800200066 17.9 21.54 0.26 0.229 0.006 4150800200067 17.9 5.04 0.10 0.233 0.006 4150800200068 17.9 2.28 0.06 0.318 0.007 4150800200069 17.9 0.53 0.02 0.124 0.004 4150800200070 17.9 0.217 0.006 0.040 0.001 4150800200071 ENDDATA 20 0 4150800200072 ENDSUBENT 71 0 4150800299999 ENDENTRY 2 0 4150899999999