ENTRY 30520 20040714 00003052000000001 SUBENT 30520001 20040714 00003052000100001 BIB 13 30 3052000100002 INSTITUTE (3BANRAM) 3052000100003 REFERENCE (J,NSE,71,208,197908) 3052000100004 (P,AECD/MISC-6,1,197809) Abstract,graph. 3052000100005 (C,75CALCUTTA,2,150,197512) 3052000100006 AUTHOR (S.Ahmad,M.M.Islam,A.H.Khan,M.Kaliquzzaman,M.Husain, 3052000100007 M.A.Rahman) 3052000100008 TITLE The energy dependence of fission fragment anisotropy 3052000100009 in fast-neutron-induced fission of uranium-235. 3052000100010 FACILITY (VDG). 3MeV 3052000100011 INC-SOURCE (P-T). Average beam current = 25 micro-amps approx. 3052000100012 SAMPLE 235U (99% enriched), about 400 micrograms/cm2 thick, 3052000100013 target diameter=1cm. 3052000100014 METHOD The 235U target was placed at an angle=45 deg. with 3052000100015 respect to the neutron beam. 3052000100016 2 fission fragment detectors were used to detect the 3052000100017 fragments at 0 and 90 deg with respect to the neutron 3052000100018 beam. 3052000100019 DETECTOR (FISCH). 2 silicon surface barrier detectors, 60 micro-3052000100020 meters thick, diameter=25mm. 3052000100021 PART-DET (FF) 3052000100022 STATUS (APRVD), M.M.Islam, 16.april 1980. data from table i of3052000100023 Nucl.Sci.Eng.,71,208. 3052000100024 HISTORY (19790927C) TL. 3052000100025 (19800508U) ML. authors approval added 3052000100026 (20040311U) SD: corrected 4-dig. year and lower cases. 3052000100027 CORRECTION The observed anisotropies were corrected for 3052000100028 - solid angles between target and detectors 3052000100029 - finite size of the target 3052000100030 - neutron flux variation across the target surface 3052000100031 - finite dimension of the detectors. 3052000100032 ENDBIB 30 0 3052000100033 NOCOMMON 0 0 3052000100034 ENDSUBENT 33 0 3052000199999 SUBENT 30520002 19840911 00003052000200001 BIB 2 5 3052000200002 REACTION (92-U-235(N,F),,DA,FF,RSD) ang. anisotropy W(0)/W(90) 3052000200003 ERR-ANALYS Statistical errors combined with uncertainties in 3052000200004 fission yield estimation (1 to 2%) due to overlap 3052000200005 between the fission-alfa and the fission-fragment 3052000200006 spectra. 3052000200007 ENDBIB 5 0 3052000200008 COMMON 1 3 3052000200009 ANG 3052000200010 ADEG 3052000200011 0.0000E+00 3052000200012 ENDCOMMON 3 0 3052000200013 DATA 4 15 3052000200014 EN EN-RSL DATA DATA-ERR 3052000200015 MEV MEV NO-DIM NO-DIM 3052000200016 3.0000E-01 7.0000E-02 9.9000E-01 2.4000E-02 3052000200017 4.0000E-01 7.0000E-02 1.0390E+00 2.9000E-02 3052000200018 5.0000E-01 7.0000E-02 1.0400E+00 2.3000E-02 3052000200019 6.0000E-01 7.0000E-02 1.0850E+00 2.3000E-02 3052000200020 7.0000E-01 6.0000E-02 1.1190E+00 2.4000E-02 3052000200021 8.0000E-01 6.0000E-02 1.1190E+00 2.0000E-02 3052000200022 9.0000E-01 6.0000E-02 1.0870E+00 2.2000E-02 3052000200023 1.0000E+00 6.0000E-02 1.1240E+00 2.5000E-02 3052000200024 1.1000E+00 5.0000E-02 1.1300E+00 2.2000E-02 3052000200025 1.2000E+00 5.0000E-02 1.1390E+00 2.3000E-02 3052000200026 1.3000E+00 4.0000E-02 1.1150E+00 2.4000E-02 3052000200027 1.4000E+00 4.0000E-02 1.1240E+00 2.6000E-02 3052000200028 1.6000E+00 4.0000E-02 1.1420E+00 2.4000E-02 3052000200029 1.8000E+00 4.0000E-02 1.1510E+00 2.0000E-02 3052000200030 2.2000E+00 3.0000E-02 1.1670E+00 2.3000E-02 3052000200031 ENDDATA 17 0 3052000200032 ENDSUBENT 31 0 3052000299999 ENDENTRY 2 0 3052099999999