ENTRY 30068 20080215 31253006800000001 SUBENT 30068001 20080215 31253006800100001 BIB 14 30 3006800100002 INSTITUTE (3HUNDEB) 3006800100003 REFERENCE (J,JNE,21,375,196704)letter to editor,description,graph3006800100004 AUTHOR (J.Csikai,S.Nagy) 3006800100005 TITLE Investigations on the angular distribution of neutron- 3006800100006 induced 238-U fission using solid state track detectors3006800100007 INC-SOURCE (D-T) Deuterium tritium reaction 3006800100008 SAMPLE Uranium layers of 1 mg/cm2 thick and 5mm diam deposited3006800100009 on 0.1 mm thick Al foil through electrolysis 3006800100010 METHOD Fission fragment detection 3006800100011 sample placed at 45 degrees with n-beam, 15 cm from 3006800100012 target. Angular dist from 0-90 and 90-180 degrees was 3006800100013 measured on independent samples(both sides of Al foil) 3006800100014 detectors were placed on circle of 10cm diam around the3006800100015 sample in a vacuum chamber 3006800100016 DETECTOR (GLASD) solid-state track detector (Zeiss glass 3006800100017 microscope cover slides). 3006800100018 MONITOR (92-U-238(N,F),,SIG) 3006800100019 Data normalized to sigma(n,f) = 1.22 barn 3006800100020 PART-DET (FF) Fission fragments 3006800100021 COMMENT In all 7500 tracks were measured in forward and back- 3006800100022 ward directions. A curve of form 3006800100023 sigma(theta) = A + B*(cos(theta))**2 3006800100024 was fitted to the data giving A= 84.9 and B= 36.3 mb/sr3006800100025 anisotropy W(0)/W(90) was 1.43 +- 0.05 in agreement 3006800100026 with previous results 3006800100027 STATUS (TABLE) Data from priv com Csikai 1/1967 3006800100028 (APRVD) approved by Peto (5/9/1972) 3006800100029 HISTORY (19701126T) previously Dastar-00158 3006800100030 (20080305A) BIB section updated 3006800100031 ERR-ANALYS (DATA-ERR) no information 3006800100032 ENDBIB 30 0 3006800100033 COMMON 1 3 3006800100034 MONIT 3006800100035 B 3006800100036 1.22 3006800100037 ENDCOMMON 3 0 3006800100038 ENDSUBENT 37 0 3006800199999 SUBENT 30068002 20080215 31253006800200001 BIB 1 1 3006800200002 REACTION (92-U-238(N,F),,DA,FF) 3006800200003 ENDBIB 1 0 3006800200004 COMMON 1 3 3006800200005 EN 3006800200006 MEV 3006800200007 1.4700E+01 3006800200008 ENDCOMMON 3 0 3006800200009 DATA 3 8 3006800200010 ANG-CM DATA-CM DATA-ERR 3006800200011 ADEG MB/SR MB/SR 3006800200012 0.0000E+00 1.2390E+02 4.8000E+00 3006800200013 7.5000E+00 1.2010E+02 4.6000E+00 3006800200014 1.8750E+01 1.1520E+02 3.1000E+00 3006800200015 3.3750E+01 1.0870E+02 3.7000E+00 3006800200016 4.8750E+01 1.0150E+02 3.0000E+00 3006800200017 6.3750E+01 9.2700E+01 2.8000E+00 3006800200018 7.5000E+01 8.8100E+01 3.9000E+00 3006800200019 8.6250E+01 8.3800E+01 2.6000E+00 3006800200020 ENDDATA 10 0 3006800200021 ENDSUBENT 20 0 3006800299999 ENDENTRY 2 0 3006899999999