ENTRY 21310 19810408 00002131000000001 SUBENT 21310001 19810408 00002131000100001 BIB 13 40 2131000100002 INSTITUTE (2FR BRC) 2131000100003 REFERENCE (W,TROCHON,800616) NUMERICAL DATA SUPERSEDING 2131000100004 DATA OF NP/A,318,1,63. 2131000100005 (J,NP/A,318,1,63,7904) MAIN REFERENCE. 2131000100006 (P,CEA-N-2037,73,7806) 2131000100007 (P,CEA-N-1969,73,7706) 2131000100008 AUTHOR (J.TROCHON,H.ABOU YEHIA,F.BRISARD,Y.PRANAL) 2131000100009 TITLE -FISSION PROPERTIES OF TH-233-. 2131000100010 FACILITY (VDG ) THE 4 MEV VAN DE GRAAFF OF BRC. 2131000100011 INC-SOURCE (P-T ) THE T(P,N)HE-3 REACTION FROM 1 TO 3 MEV. 2131000100012 (D-D ) THE D(D,N)HE-3 REACTION FROM 4 TO 6 MEV. 2131000100013 .GAS TARGETS WERE USED IN BOTH CASES. 2131000100014 SAMPLE .THORIUM TETRAFLUORIDE, ABOUT 0.08 MG/CM2 THICK, 2131000100015 VACUUM EVAPORATED ONTO A CARBON FOIL 1.9 CM IN DIA. 2131000100016 METHOD (COINC) RECORDING THE AMPLITUDE OF COINCIDENCE PULSES 2131000100017 FROM EACH PAIR OF DETECTORS. 2131000100018 DETECTOR (SOLST) TREE SURFACE BARRIER DETECTORS. 2131000100019 .THE DETECTORS WERE ABSOLUTE ENERGY CALIBRATED FROM 2131000100020 MEASUREMENT OF FRAGMENT PULSE HEIGHTS IN THE THERMAL 2131000100021 FISSION OF U-235. 2131000100022 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2131000100023 HISTORY (800205C) CN. 2131000100024 (800213E) 2131000100025 (800616A) G.C., UPDATED FOR NUMERICAL DATA OF 2131000100026 PRIVATE COMMUNICATION OF TROCHON (BETTER FF 2131000100027 ANISOTROPY CORRECTION). 2131000100028 (800718E) 2131000100029 CORRECTION .NEUTRON TIME OF FLIGHT WAS STORED TO CORRECT THE 2131000100030 EXPERIMENTAL SPECTRA FOR THE BACKGROUND DUE TO 2131000100031 FISSION EVENTS INDUCED BY SCATTERED NEUTRONS. 2131000100032 .TO OBTAIN THE PRIMARY MASSES OF THE FISSION FRAGMENTS 2131000100033 BEFORE NEUTRON EMISSION, THE KINETIC ENERGIES HAVE 2131000100034 BEEN CORRECTED FOR, 2131000100035 -THE CENTER OF MASS MOTION, 2131000100036 -THE DIFFERENCE OF ENERGY LOSSES IN THE MATERIALS 2131000100037 TRAVERSED BY THE FISSION FRAGMENTS DUE TO THE 2131000100038 DIFFERENT ANGULAR DISTRIBUTIONS AT VARIOUS INCIDENT 2131000100039 NEUTRON ENERGIES, 2131000100040 -THE PROMPT NEUTRON EMMISION. 2131000100041 ERR-ANALYS .STATISTICAL ERRORS GIVEN. 2131000100042 ENDBIB 40 0 2131000100043 NOCOMMON 0 0 2131000100044 ENDSUBENT 43 0 2131000199999 SUBENT 21310002 19800718 00002131000200001 BIB 3 6 2131000200002 REACTION (90-TH-232(N,F),,AKE,FF) 2131000200003 STATUS .TABLE 1 IN MAIN REFERENCE. 2131000200004 HISTORY (800205C) 2131000200005 (800213E) 2131000200006 (800616A) G.C. UPDATED. 2131000200007 (800718E) 2131000200008 ENDBIB 6 0 2131000200009 NOCOMMON 0 0 2131000200010 DATA 4 13 2131000200011 EN EN-RSL DATA DATA-ERR 2131000200012 MEV MEV MEV MEV 2131000200013 1.3500E+00 2.0000E-02 1.6328E+02 1.3000E-01 2131000200014 1.4300E+00 2.0000E-02 1.6331E+02 1.1000E-01 2131000200015 1.6000E+00 2.0000E-02 1.6322E+02 7.0000E-02 2131000200016 1.6800E+00 2.0000E-02 1.6361E+02 7.0000E-02 2131000200017 1.7200E+00 2.0000E-02 1.6336E+02 7.0000E-02 2131000200018 1.7700E+00 2.0000E-02 1.6363E+02 8.0000E-02 2131000200019 1.8800E+00 2.0000E-02 1.6327E+02 7.0000E-02 2131000200020 2.0000E+00 2.0000E-02 1.6349E+02 7.0000E-02 2131000200021 2.2000E+00 2.0000E-02 1.6338E+02 6.0000E-02 2131000200022 2.4000E+00 2.0000E-02 1.6403E+02 5.0000E-02 2131000200023 2.9600E+00 2.0000E-02 1.6427E+02 6.0000E-02 2131000200024 4.2000E+00 1.1000E-01 1.6477E+02 1.0000E-01 2131000200025 5.3000E+00 1.1000E-01 1.6497E+02 6.0000E-02 2131000200026 ENDDATA 15 0 2131000200027 ENDSUBENT 26 0 2131000299999 SUBENT 21310003 19801103 00002131000300001 BIB 4 7 2131000300002 REACTION (90-TH-232(N,F),,AP) MEAN MASS OF THE PRIMARY HEAVY 2131000300003 FRAGMENT. 2131000300004 COMMENT .THE PRIMARY MASS HAVE BEEN CALCULATED , USING THE 2131000300005 MEASURED KINETIC ENERGIES. 2131000300006 STATUS .TABLE 1 IN MAIN REFERENCE. 2131000300007 (DEP,21310002) 2131000300008 HISTORY (800205C) 2131000300009 ENDBIB 7 0 2131000300010 NOCOMMON 0 0 2131000300011 DATA 3 13 2131000300012 EN EN-RSL DATA 2131000300013 MEV MEV NO-DIM 2131000300014 1.3500E+00 2.0000E-02 1.4087E+02 2131000300015 1.4300E+00 2.0000E-02 1.4083E+02 2131000300016 1.6000E+00 2.0000E-02 1.4086E+02 2131000300017 1.6800E+00 2.0000E-02 1.4085E+02 2131000300018 1.7200E+00 2.0000E-02 1.4094E+02 2131000300019 1.7700E+00 2.0000E-02 1.4085E+02 2131000300020 1.8800E+00 2.0000E-02 1.4090E+02 2131000300021 2.0000E+00 2.0000E-02 1.4096E+02 2131000300022 2.2000E+00 2.0000E-02 1.4073E+02 2131000300023 2.4000E+00 2.0000E-02 1.4071E+02 2131000300024 2.9600E+00 2.0000E-02 1.4035E+02 2131000300025 4.2000E+00 1.1000E-01 1.3937E+02 2131000300026 5.3000E+00 1.1000E-01 1.3944E+02 2131000300027 ENDDATA 15 0 2131000300028 ENDSUBENT 27 0 2131000399999 ENDENTRY 3 0 2131099999999