ENTRY 41173 20091112 41484117300000001 SUBENT 41173001 20091112 41484117300100001 BIB 13 40 4117300100002 INSTITUTE (4RUSEPA) 4117300100003 REFERENCE (J,YF,33,(3),620,198103) Data are given. 4117300100004 (J,SNP,33,324,198103) English of YF 33 620 . 4117300100005 AUTHOR (E.F.Fomushkin, G.F.Novoselov, Yu.I.Vinogradov, 4117300100006 V.V.Gavrilov, V.I.In'kov, B.K.Maslennikov, V.P.Polynov,4117300100007 V.M.Surin, A.M.Shvetsov) 4117300100008 TITLE Measurement of the energy dependence of the neutron 4117300100009 fission cross section of Am-242m. 4117300100010 SAMPLE Am-242-M prepared by electromagnetic separation. 4117300100011 Am-241 content is 13.4 +-0.06 %, 4117300100012 Am-243 content is 0.492 +-0.015 %,relative to Am-242m 4117300100013 immediately after separation. 4117300100014 The number of Am-242m nuclei in layers was determined 4117300100015 by alpha-activity of Cm-242 in equilibrium with 4117300100016 Am-242m by semiconductor alpha-spectrometer. 4117300100017 DECAY-DATA (95-AM-242-M,141.YR,B-,,0.830) IT - 0.995 4117300100018 HL=141+-2 yr, probability for isomeric transition 4117300100019 99.5+-0.5 % , for Beta- decay 83.0+-0.5 % . 4117300100020 (96-CM-242,162.8D) HL=162.8+-0.4 days. 4117300100021 Decay data used to define Am-242m nuclei in samples. 4117300100022 DETECTOR (TRD) Dielectric track detector . 4117300100023 MONITOR (92-U-235(N,F),,SIG) 4117300100024 MONIT-REF (,V.A.Konshin+,J,YK,1979,(3/34),3,1979) 4117300100025 CORRECTION Correction to background , for spontaneous 4117300100026 fission , for secondary neutrons fission , 4117300100027 for fission anisotropy , for fission of Am-241 present4117300100028 in sample, for fission of Am-243, Pu-238, Pu-242 and 4117300100029 other nuclides. 4117300100030 ERR-ANALYS (ERR-1) Error in c-s due to determining the amounts of 4117300100031 nuclei in layers (standard deviation). 4117300100032 (DATA-ERR) Standard deviation includes statistical and 4117300100033 uncertainty due to corrections for background and for 4117300100034 the fission of Am-241,Am-243 and other nuclides 4117300100035 present in samples. 4117300100036 STATUS Data are taken from the reference 4117300100037 HISTORY (19950623C) + + Compiled at the centre - CJD + + 4117300100038 (20010311A) Date and INSTITUTE codes are corrected. 4117300100039 (20091112U) M.M. TITLE line was added. 4117300100040 Free text was corrected to be human-readable. 4117300100041 ERR-S -> DATA-ERR. 4117300100042 ENDBIB 40 0 4117300100043 COMMON 1 3 4117300100044 ERR-1 4117300100045 PER-CENT 4117300100046 4.8 4117300100047 ENDCOMMON 3 0 4117300100048 ENDSUBENT 47 0 4117300199999 SUBENT 41173002 20091112 41484117300200001 BIB 5 7 4117300200002 REACTION (95-AM-242-M(N,F),,SIG) 4117300200003 FACILITY (VDG) Neutron generator NG-150.Deutrons of 130-140 keV.4117300200004 INC-SOURCE (D-T) 4117300200005 ADD-RES Angular distribution of FF can described by sum of 4117300200006 zero and second Legendre polynomials with relative 4117300200007 value of anisotropic component a2/a0=0.116+-0.004 . 4117300200008 STATUS (TABLE) Table I of J,YF,33,(3),620,1981 . 4117300200009 ENDBIB 7 0 4117300200010 NOCOMMON 0 0 4117300200011 DATA 4 1 4117300200012 EN EN-ERR DATA DATA-ERR 4117300200013 MEV MEV B PER-CENT 4117300200014 14.8 0.125 2.305 2.2 4117300200015 ENDDATA 3 0 4117300200016 ENDSUBENT 15 0 4117300299999 SUBENT 41173003 20091112 41484117300300001 BIB 6 14 4117300300002 REACTION (95-AM-242-M(N,F),,SIG) 4117300300003 SAMPLE Diameter of Am, U targets 5 mm. 4117300300004 FACILITY (VDG) Neutron generator EG-5 4117300300005 INC-SOURCE (P-T) Tritiated titanium target od 5 mm diameter, 4117300300006 1.65 mg/cm**2 thickness. Assembly of layers and 4117300300007 detector film was screened with Cd cover of 0.1 mm 4117300300008 thickness. 4117300300009 ERR-ANALYS Error due to measured component of background due to 4117300300010 evaporation neutrons - < 6.5 % . 4117300300011 Statistical error in the ratio of events counts in 4117300300012 Am-242m and U-235 < 2.3%. 4117300300013 Error due to dependence of FF registration efficiency4117300300014 from angular anisotropy in fission process < 1.% . 4117300300015 STATUS (TABLE) Table I of J,YF,33,(3),620,1981 . 4117300300016 ENDBIB 14 0 4117300300017 NOCOMMON 0 0 4117300300018 DATA 4 20 4117300300019 EN EN-ERR DATA DATA-ERR 4117300300020 MEV MEV B PER-CENT 4117300300021 1.000 0.090 1.701 2.2 4117300300022 1.105 0.085 1.728 2.1 4117300300023 1.210 0.085 1.570 1.7 4117300300024 1.310 0.080 1.585 1.6 4117300300025 1.415 0.080 1.602 2.0 4117300300026 1.515 0.080 1.667 2.1 4117300300027 1.620 0.080 1.592 1.8 4117300300028 1.720 0.080 1.586 1.6 4117300300029 1.820 0.080 1.561 2.7 4117300300030 1.975 0.080 1.453 1.7 4117300300031 2.130 0.080 1.644 1.5 4117300300032 2.280 0.080 1.652 1.7 4117300300033 2.430 0.085 1.611 2.8 4117300300034 2.730 0.085 1.571 1.6 4117300300035 3.030 0.090 1.569 1.9 4117300300036 3.330 0.090 1.677 2.9 4117300300037 3.630 0.095 1.592 1.4 4117300300038 3.930 0.100 1.597 1.8 4117300300039 4.230 0.105 1.566 2.1 4117300300040 4.520 0.110 1.596 3.5 4117300300041 ENDDATA 22 0 4117300300042 ENDSUBENT 41 0 4117300399999 SUBENT 41173004 20091112 41484117300400001 BIB 5 5 4117300400002 REACTION (95-AM-242-M(N,F),,SIG,,AV) 4117300400003 INC-SOURCE (EXPLO) 4117300400004 METHOD (TOF) Time resolution 9.3 nsec/m (FWHM) 4117300400005 CORRECTION Background less 2% . 4117300400006 STATUS (TABLE) Table II of J,YF,33,(3),620,1981 . 4117300400007 ENDBIB 5 0 4117300400008 COMMON 1 3 4117300400009 EN-RSL-FW 4117300400010 NSEC/M 4117300400011 9.3 4117300400012 ENDCOMMON 3 0 4117300400013 DATA 4 14 4117300400014 EN-MIN EN-MAX DATA DATA-ERR 4117300400015 MEV MEV B PER-CENT 4117300400016 0.04 0.05 3.810 4.3 4117300400017 0.05 0.06 3.676 4.2 4117300400018 0.06 0.08 2.815 3.8 4117300400019 0.08 0.10 3.132 3.9 4117300400020 0.10 0.15 2.837 3.0 4117300400021 0.15 0.20 2.751 2.9 4117300400022 0.20 0.30 2.260 2.5 4117300400023 0.30 0.40 2.108 2.8 4117300400024 0.40 0.60 1.691 2.2 4117300400025 0.60 0.80 1.490 2.3 4117300400026 0.80 1.00 1.584 2.4 4117300400027 1.00 1.30 1.661 2.2 4117300400028 1.30 1.60 1.538 2.2 4117300400029 1.60 2.00 1.598 2.1 4117300400030 ENDDATA 16 0 4117300400031 ENDSUBENT 30 0 4117300499999 ENDENTRY 4 0 4117399999999