ENTRY 10925 20141219 14051092500000001 SUBENT 10925001 20141219 14051092500100001 BIB 10 19 1092500100002 TITLE Fragment Mass and Kinetic-Energy Distributions from 1092500100003 Spontaneous Fission of the Neutron-Deficient Isotopes, 1092500100004 1.2-s 246Fm and 38-s 248Fm 1092500100005 AUTHOR (D.Hoffman,D.Lee,A.Ghiorso,M.Nurmia,K.Aleklett) 1092500100006 REFERENCE (J,PR/C,22,1581,198010) 1092500100007 #doi:10.1103/PhysRevC.22.1581 1092500100008 INSTITUTE (1USALRL,1USALAS,2SWDSWR) 1092500100009 FACILITY (CYCLO,1USABRK) 1092500100010 PART-DET (FF) 1092500100011 METHOD (COINC) 1092500100012 DETECTOR (SIBAR) Four pairs of stationary Si(Au) solid-state 1092500100013 detectors, calibrated using Cf-252 sources. 1092500100014 Coincidence detection efficiency was about 65%. 1092500100015 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 1092500100016 HISTORY (19830913C) 1092500100017 (20141219A) BP: Updated to new date formats,lower 1092500100018 case. corrections according last EXFOR rules and 1092500100019 Dict. Corrected title, added doi, digitized Fig. 2., 1092500100020 updated information. 1092500100021 ENDBIB 19 0 1092500100022 NOCOMMON 0 0 1092500100023 ENDSUBENT 22 0 1092500199999 SUBENT 10925002 20141219 14051092500200001 BIB 3 3 1092500200002 REACTION (100-FM-246(0,F)MASS,PRE,FY) 1092500200003 STATUS (CURVE) Fig. 2, page 1582. 1092500200004 DECAY-DATA (100-FM-246,1.2SEC,SF) 1092500200005 ENDBIB 3 0 1092500200006 NOCOMMON 0 0 1092500200007 DATA 3 27 1092500200008 MASS DATA DATA-ERR 1092500200009 NO-DIM PC/FIS PC/FIS 1092500200010 83.922 0.330 0.204 1092500200011 86.902 0.424 0.220 1092500200012 89.725 0.565 0.267 1092500200013 92.863 0.832 0.283 1092500200014 95.843 1.743 0.377 1092500200015 98.980 2.105 0.455 1092500200016 101.961 4.838 0.644 1092500200017 104.941 4.853 0.660 1092500200018 107.922 5.403 0.675 1092500200019 110.902 4.335 0.613 1092500200020 114.039 3.361 0.518 1092500200021 116.863 2.168 0.471 1092500200022 119.686 1.618 0.361 1092500200023 122.823 1.037 0.283 1092500200024 125.804 1.618 0.377 1092500200025 128.784 2.152 0.440 1092500200026 131.921 3.377 0.518 1092500200027 135.059 4.335 0.597 1092500200028 138.039 5.372 0.675 1092500200029 141.176 4.822 0.660 1092500200030 144.157 4.822 0.644 1092500200031 146.823 2.089 0.455 1092500200032 150.118 1.728 0.408 1092500200033 152.941 0.817 0.267 1092500200034 155.921 0.565 0.267 1092500200035 159.059 0.377 0.188 1092500200036 161.882 0.283 0.204 1092500200037 ENDDATA 29 0 1092500200038 ENDSUBENT 37 0 1092500299999 SUBENT 10925003 20141219 14051092500300001 BIB 3 3 1092500300002 REACTION (100-FM-248(0,F)MASS,PRE,FY) 1092500300003 STATUS (CURVE) Fig. 2, page 1582. 1092500300004 DECAY-DATA (100-FM-248,38.SEC,SF) 1092500300005 ENDBIB 3 0 1092500300006 NOCOMMON 0 0 1092500300007 DATA 3 15 1092500300008 MASS DATA DATA-ERR 1092500300009 NO-DIM PC/FIS PC/FIS 1092500300010 89.066 0.538 0.394 1092500300011 93.920 2.160 0.882 1092500300012 98.931 2.522 0.898 1092500300013 104.099 3.357 0.992 1092500300014 108.953 5.577 1.244 1092500300015 114.120 4.459 0.976 1092500300016 118.818 1.073 0.535 1092500300017 123.985 0.554 0.425 1092500300018 128.840 1.089 0.567 1092500300019 134.163 4.459 0.976 1092500300020 139.018 5.546 1.260 1092500300021 143.872 3.357 0.992 1092500300022 149.039 2.506 0.898 1092500300023 154.050 2.176 0.850 1092500300024 159.061 0.522 0.394 1092500300025 ENDDATA 17 0 1092500300026 ENDSUBENT 25 0 1092500399999 SUBENT 10925004 20141219 14051092500400001 BIB 4 5 1092500400002 REACTION (100-FM-246(0,F),PRE,AKE,LF+HF) 1092500400003 CORRECTION Neutron correction performed by considering the 1092500400004 neutron multiplicity distribution curve 1092500400005 STATUS (TABLE) page 1583. 1092500400006 DECAY-DATA (100-FM-246,1.2SEC,SF) 1092500400007 ENDBIB 5 0 1092500400008 NOCOMMON 0 0 1092500400009 DATA 2 1 1092500400010 DATA DATA-ERR 1092500400011 MEV MEV 1092500400012 199.0 4.0 1092500400013 ENDDATA 3 0 1092500400014 ENDSUBENT 13 0 1092500499999 SUBENT 10925005 20141219 14051092500500001 BIB 4 5 1092500500002 REACTION (100-FM-248(0,F),PRE,AKE,LF+HF) 1092500500003 CORRECTION Neutron correction performed by considering the 1092500500004 neutron multiplicity distribution curve 1092500500005 STATUS (TABLE) page 1583. 1092500500006 DECAY-DATA (100-FM-248,38.SEC,SF) 1092500500007 ENDBIB 5 0 1092500500008 NOCOMMON 0 0 1092500500009 DATA 2 1 1092500500010 DATA DATA-ERR 1092500500011 MEV MEV 1092500500012 198.0 4.0 1092500500013 ENDDATA 3 0 1092500500014 ENDSUBENT 13 0 1092500599999 ENDENTRY 5 0 1092599999999