ENTRY 21576 19810408 00002157600000001 SUBENT 21576001 19810408 00002157600100001 BIB 13 34 2157600100002 INSTITUTE (2FR BRC) 2157600100003 REFERENCE (W,TROCHON,800616) NUMERICAL DATA 2157600100004 (J,NP/A,318,1,63,7904) EXPERIMENTAL METHOD. 2157600100005 (R,CEA-N-2080,101,7905) 2157600100006 AUTHOR (H.ABOU YEHIA,F.BRISARD,Y.PRANAL,J.TROCHON) 2157600100007 TITLE -STUDY OF THE KINETIC ENERGY OF THE FISSION FRAGMENTS 2157600100008 OF THE REACTION U-238(N,F).-(IN FRENCH).- 2157600100009 FACILITY (VDG ) THE 4 MEV VAN DE GRAAFF OF BRC. 2157600100010 INC-SOURCE (P-T ) THE T(P,N)HE-3 REACTION FROM 1 TO 3 MEV. 2157600100011 (D-D ) THE D(D,N)HE-3 REACTION FROM 4 TO 6 MEV. 2157600100012 .GAS TARGETS WERE USED IN BOTH CASES. 2157600100013 SAMPLE .NO DETAILS. 2157600100014 METHOD (COINC) RECORDING THE AMPLITUDE OF COINCIDENCE PULSES 2157600100015 FROM EACH PAIR OF DETECTORS. 2157600100016 DETECTOR (SOLST) TREE SURFACE BARRIER DETECTORS. 2157600100017 .THE DETECTORS WERE ABSOLUTE ENERGY CALIBRATED FROM 2157600100018 MEASUREMENT OF FRAGMENT PULSE HEIGHTS IN THE THERMAL 2157600100019 FISSION OF U-235. 2157600100020 STATUS .DATA TAKEN FROM PRIVATE PUBLICATION. 2157600100021 HISTORY (800616C) G.C. 2157600100022 (800718E) 2157600100023 CORRECTION .NEUTRON TIME OF FLIGHT WAS STORED TO CORRECT THE 2157600100024 EXPERIMENTAL SPECTRA FOR THE BACKGROUND DUE TO 2157600100025 FISSION EVENTS INDUCED BY SCATTERED NEUTRONS. 2157600100026 .TO OBTAIN THE PRIMARY MASSES OF THE FISSION FRAGMENTS 2157600100027 BEFORE NEUTRON EMISSION, THE KINETIC ENERGIES HAVE 2157600100028 BEEN CORRECTED FOR, 2157600100029 -THE CENTER OF MASS MOTION, 2157600100030 -THE DIFFERENCE OF ENERGY LOSSES IN THE MATERIALS 2157600100031 TRAVERSED BY THE FISSION FRAGMENTS DUE TO THE 2157600100032 DIFFERENT ANGULAR DISTRIBUTIONS AT VARIOUS INCIDENT 2157600100033 NEUTRON ENERGIES, 2157600100034 -THE PROMPT NEUTRON EMMISION. 2157600100035 ERR-ANALYS .STATISTICAL ERRORS GIVEN. 2157600100036 ENDBIB 34 0 2157600100037 NOCOMMON 0 0 2157600100038 ENDSUBENT 37 0 2157600199999 SUBENT 21576002 19800718 00002157600200001 BIB 3 4 2157600200002 REACTION (92-U-238(N,F),,AKE,FF) 2157600200003 STATUS .TABLE FROM PRIVATE COMMUNICATION. 2157600200004 HISTORY (800616C) G.C. 2157600200005 (800718E) 2157600200006 ENDBIB 4 0 2157600200007 NOCOMMON 0 0 2157600200008 DATA 4 14 2157600200009 EN EN-RSL DATA DATA-ERR 2157600200010 MEV MEV MEV MEV 2157600200011 9.2000E-01 2.0000E-02 1.7436E+02 1.8000E-01 2157600200012 1.0500E+00 2.0000E-02 1.7423E+02 1.9000E-01 2157600200013 1.1700E+00 2.0000E-02 1.7417E+02 1.2000E-01 2157600200014 1.2300E+00 2.0000E-02 1.7429E+02 1.3000E-01 2157600200015 1.3500E+00 2.0000E-02 1.7424E+02 1.1000E-01 2157600200016 1.5000E+00 2.0000E-02 1.7429E+02 9.0000E-02 2157600200017 1.7000E+00 2.0000E-02 1.7438E+02 1.6000E-01 2157600200018 1.9000E+00 2.0000E-02 1.7401E+02 7.0000E-02 2157600200019 2.0000E+00 2.0000E-02 1.7418E+02 9.0000E-02 2157600200020 2.5000E+00 2.0000E-02 1.7411E+02 8.0000E-02 2157600200021 2.7000E+00 2.0000E-02 1.7402E+02 1.1000E-01 2157600200022 2.9900E+00 2.0000E-02 1.7402E+02 9.0000E-02 2157600200023 5.0000E+00 1.0000E-01 1.7368E+02 7.0000E-02 2157600200024 6.0000E+00 7.0000E-02 1.7375E+02 7.0000E-02 2157600200025 ENDDATA 16 0 2157600200026 ENDSUBENT 25 0 2157600299999 ENDENTRY 2 0 2157699999999