ENTRY 30694 20090905 31403069400000001 SUBENT 30694001 20090905 31403069400100001 BIB 15 34 3069400100002 INSTITUTE (3CPRAEP) 3069400100003 REFERENCE (J,CNP,3,(1),39,198102) in Chinese, English abstract 3069400100004 AUTHOR (Zhou Shuhua, Guo Shilun, Meng Wu, Sun Shengfen, 3069400100005 Hao Xiuhong) 3069400100006 TITLE Angular distributions of fission fragments at the 3069400100007 U-238(n,2nf) threshold 3069400100008 FACILITY (VDG,3CPRAEP) 2.5 MV Van de Graaff 3069400100009 INC-SOURCE (D-T) 0.6125 MeV deuterons on 0.5 milli-gram/cm2 3069400100010 titanium tritide target. 3069400100011 SAMPLE Natural uranium sample,thickness=1 milli-gram/cm2, 3069400100012 area=6x6 mm2,electroplated on 0.2 mm thick aluminium 3069400100013 backing. 3069400100014 METHOD Direct detection of fission fragments 3069400100015 DETECTOR (TRD) 87x10 mm2 Mica detector surrounding the fission 3069400100016 sample used for fragment measurement. 3069400100017 ANALYSIS Least square Legendre fit for angular distribution, 3069400100018 Legendre-coefficients of the form 3069400100019 W(theta)=sum(a(l)*p(l)) 3069400100020 Theta is the angle of the fragment with respect to the 3069400100021 incident neutrons in the centre-of-mass system. As the 3069400100022 angular distribution is symmetric at 90 degrees, only 3069400100023 even terms occur in the polynomial. 3069400100024 PART-DET (FF) Fission fragments 3069400100025 CORRECTION Data have been corrected for the definite size of 3069400100026 fission sample and detector, and the fragment detection3069400100027 efficiency difference in different angles. The neutron 3069400100028 source was regarded as a point source. 3069400100029 ERR-ANALYS (ERR-S) Errors given in the data Table are only 3069400100030 statistical. 3069400100031 The energy resolution is due to the energy spread of 3069400100032 deuterons and the angle subtended by the fission sample3069400100033 STATUS (TABLE) Data from Table I of article 3069400100034 HISTORY (19850208C) Compiled by Liang Qichang 3069400100035 (20090725A) SD:Updated to new date formats,lower case. 3069400100036 ENDBIB 34 0 3069400100037 NOCOMMON 0 0 3069400100038 ENDSUBENT 37 0 3069400199999 SUBENT 30694002 20090905 31403069400200001 BIB 1 1 3069400200002 REACTION (92-U-238(N,F),,DA,FF,LEG/RSD) 3069400200003 ENDBIB 1 0 3069400200004 NOCOMMON 0 0 3069400200005 DATA 5 40 3069400200006 EN EN-RSL NUMBER-CM DATA-CM ERR-S 3069400200007 MEV MEV NO-DIM NO-DIM NO-DIM 3069400200008 1.2750E+01 8.0000E-02 0.0000E+00 1.0440E+00 1.2000E-02 3069400200009 1.2750E+01 8.0000E-02 2.0000E+00 1.4100E-01 2.3000E-02 3069400200010 1.2750E+01 8.0000E-02 4.0000E+00 7.0000E-02 3.0000E-02 3069400200011 1.2950E+01 8.0000E-02 0.0000E+00 1.0350E+00 1.2000E-02 3069400200012 1.2950E+01 8.0000E-02 2.0000E+00 5.9000E-02 2.5000E-02 3069400200013 1.2950E+01 8.0000E-02 4.0000E+00 3.2000E-02 3.3000E-02 3069400200014 1.2950E+01 8.0000E-02 6.0000E+00 5.5000E-02 3.8000E-02 3069400200015 1.3250E+01 7.0000E-02 0.0000E+00 1.0800E+00 1.1000E-02 3069400200016 1.3250E+01 7.0000E-02 2.0000E+00 1.6000E-01 1.9000E-02 3069400200017 1.3660E+01 6.0000E-02 0.0000E+00 1.0880E+00 1.2000E-02 3069400200018 1.3660E+01 6.0000E-02 2.0000E+00 1.7600E-01 2.0000E-02 3069400200019 1.3830E+01 6.0000E-02 0.0000E+00 1.0560E+00 1.2000E-02 3069400200020 1.3830E+01 6.0000E-02 2.0000E+00 1.6200E-01 2.3000E-02 3069400200021 1.3830E+01 6.0000E-02 4.0000E+00 6.8000E-02 2.9000E-02 3069400200022 1.4130E+01 8.0000E-02 0.0000E+00 1.0690E+00 1.3000E-02 3069400200023 1.4130E+01 8.0000E-02 2.0000E+00 1.6800E-01 2.4000E-02 3069400200024 1.4130E+01 8.0000E-02 4.0000E+00 4.0000E-02 3.0000E-02 3069400200025 1.4320E+01 8.0000E-02 0.0000E+00 1.1060E+00 1.2000E-02 3069400200026 1.4320E+01 8.0000E-02 2.0000E+00 2.1200E-01 2.1000E-02 3069400200027 1.4630E+01 1.1000E-01 0.0000E+00 1.1020E+00 1.1000E-02 3069400200028 1.4630E+01 1.1000E-01 2.0000E+00 2.0500E-01 1.9000E-02 3069400200029 1.4810E+01 1.2000E-01 0.0000E+00 1.0900E+00 1.2000E-02 3069400200030 1.4810E+01 1.2000E-01 2.0000E+00 2.1600E-01 2.3000E-02 3069400200031 1.4810E+01 1.2000E-01 4.0000E+00 4.3000E-02 3.0000E-02 3069400200032 1.5110E+01 1.4000E-01 0.0000E+00 1.0950E+00 1.0000E-02 3069400200033 1.5110E+01 1.4000E-01 2.0000E+00 1.8900E-01 1.7000E-02 3069400200034 1.5400E+01 1.5000E-01 0.0000E+00 1.0980E+00 1.0000E-02 3069400200035 1.5400E+01 1.5000E-01 2.0000E+00 2.1000E-01 2.0000E-02 3069400200036 1.5400E+01 1.5000E-01 4.0000E+00 6.6000E-02 2.7000E-02 3069400200037 1.5400E+01 1.5000E-01 6.0000E+00 5.7000E-02 3.1000E-02 3069400200038 1.5530E+01 1.6000E-01 0.0000E+00 1.1300E+00 1.1000E-02 3069400200039 1.5530E+01 1.6000E-01 2.0000E+00 2.5900E-01 2.1000E-02 3069400200040 1.5530E+01 1.6000E-01 4.0000E+00 3.3000E-02 2.8000E-02 3069400200041 1.5530E+01 1.6000E-01 6.0000E+00 3.9000E-02 3.3000E-02 3069400200042 1.5850E+01 1.8000E-01 0.0000E+00 1.0900E+00 9.0000E-03 3069400200043 1.5850E+01 1.8000E-01 2.0000E+00 2.4200E-01 1.7000E-02 3069400200044 1.5850E+01 1.8000E-01 4.0000E+00 8.1000E-02 2.1000E-02 3069400200045 1.6030E+01 2.0000E-01 0.0000E+00 1.1030E+00 1.0000E-02 3069400200046 1.6030E+01 2.0000E-01 2.0000E+00 2.4400E-01 1.9000E-02 3069400200047 1.6030E+01 2.0000E-01 4.0000E+00 5.1000E-02 2.5000E-02 3069400200048 ENDDATA 42 0 3069400200049 ENDSUBENT 48 0 3069400299999 SUBENT 30694003 20090905 31403069400300001 BIB 2 3 3069400300002 REACTION (92-U-238(N,F),,DA,FF,RSD) Angular anisotropy 3069400300003 COMMENT Angular distribution of fission fragments at zero 3069400300004 degree relative to 90 degrees given in data Table. 3069400300005 ENDBIB 3 0 3069400300006 COMMON 1 3 3069400300007 ANG-CM 3069400300008 ADEG 3069400300009 0.0000E+00 3069400300010 ENDCOMMON 3 0 3069400300011 DATA 4 14 3069400300012 EN EN-RSL DATA ERR-S 3069400300013 MEV MEV NO-DIM NO-DIM 3069400300014 1.2750E+01 8.0000E-02 1.2550E+00 3.2000E-02 3069400300015 1.2950E+01 8.0000E-02 1.1800E+00 4.4000E-02 3069400300016 1.3250E+01 7.0000E-02 1.2410E+00 2.8000E-02 3069400300017 1.3660E+01 6.0000E-02 1.2640E+00 3.0000E-02 3069400300018 1.3830E+01 6.0000E-02 1.2860E+00 3.2000E-02 3069400300019 1.4130E+01 8.0000E-02 1.2770E+00 3.3000E-02 3069400300020 1.4320E+01 8.0000E-02 1.3180E+00 3.1000E-02 3069400300021 1.4630E+01 1.1000E-01 1.3070E+00 2.8000E-02 3069400300022 1.4810E+01 1.2000E-01 1.3540E+00 3.3000E-02 3069400300023 1.5110E+01 1.4000E-01 1.2840E+00 2.4000E-02 3069400300024 1.5400E+01 1.5000E-01 1.4310E+00 3.6000E-02 3069400300025 1.5530E+01 1.6000E-01 1.4600E+00 3.8000E-02 3069400300026 1.5850E+01 1.8000E-01 1.4130E+00 2.4000E-02 3069400300027 1.6030E+01 2.0000E-01 1.3980E+00 2.7000E-02 3069400300028 ENDDATA 16 0 3069400300029 ENDSUBENT 28 0 3069400399999 ENDENTRY 3 0 3069499999999