ENTRY 20600 19840126 00002060000000001 SUBENT 20600001 19840126 00002060000100001 BIB 16 46 2060000100002 INSTITUTE (2FR SAC) 2060000100003 REFERENCE (T,SIMON,,76) NU-PROMPT AND PROMPT FISSION GAMMA 2060000100004 ENERGY TABULATED (IN FRENCH). 2060000100005 (C,75KIEV,5,337,7506) (G.SIMON,J.FREHAUT) SAME 2060000100006 EXPERIMENT FOR PU-241 ONLY. 2060000100007 AUTHOR (G.SIMON) 2060000100008 TITLE -MEASUREMENTS AND INTERPRETATION OF THE MEAN PROMPT 2060000100009 NEUTRON NUMBER AND THE MEAN PROMPT FISSION GAMMA 2060000100010 ENERGY EMMITED IN NEUTRON RESONANCES OF FISSILE 2060000100011 NUCLEI- 2060000100012 FACILITY (LINAC) 60 MEV SACLAY ELECTRON LINAC 2060000100013 INC-SOURCE (PHOTO) PHOTO-NEUTRONS EMMITED IN A NATURAL-U 2060000100014 TARGET AND MODERATED IN POLYETHYLENE. 2060000100015 SAMPLE .ENRICHED URANIUM OXIDE DEPOSED ON AL DISKS, 2060000100016 THICKNESS 1 MG/CM**2,3 CM DIAMETER. 2060000100017 .ISOTOPIC CONTENT IN ATOMS PER-CENT, 2060000100018 U-234 = 0.02, U-235 = 99.87, U-236 = 0.04, 2060000100019 U-238 = 0.07 2060000100020 METHOD (TOF ) 30 M FLIGHT PATH. 2060000100021 (COINC) COINCIDENCE BETWEEN PROMPT FISSION 2060000100022 GAMMAS AND FISSION FRAGMENTS 2060000100023 DETECTOR (STANK) FOR FISSION NEUTRONS AND GAMMAS, BIG 2060000100024 SPHERICAL LIQUID SCINTILLATOR DOPPED WITH GD,1 M 2060000100025 DIAMETER 2060000100026 (FISCH) FOR FISSION FRAGMENTS,IONIZATION FISSION 2060000100027 CHAMBER FILLED WITH AR AND METHANE AT 3 ATM. 2060000100028 ANALYSIS .RESONANCE ENERGIES TAKEN FROM J.BLONS,ET AL.,PROC. 2060000100029 CONF.71KNOXVILLE,829,(1971) AND FROM A.MICHAUDON, 2060000100030 ET AL.,NUCL.PHYS.,69(1965)545. 2060000100031 PART-DET (FF ) FISSION FRAGMENTS, 2060000100032 (G ) GAMMAS, 2060000100033 (N ) PROMPT FISSION NEUTRONS. 2060000100034 COMMENT .ANTICORRELATED FLUCTUATIONS BETWEEN NU-PROMPT AND 2060000100035 THE MEAN GAMMA-RAY ENERGY FOUND WEAK AND ENTIRELY 2060000100036 ATTRIBUTED TO (N,GAMMA F) REACTION. 2060000100037 STATUS .DATA TAKEN FROM TABLE 8 OF G.SIMON THESIS. 2060000100038 HISTORY (760729C) 2060000100039 (761217E) 2060000100040 (800603E) 2060000100041 CORRECTION .DIFFERENCE BETWEEN FISSION NEUTRON SPECTRA OF 2060000100042 CF-252 AND U-235 ACCOUNTED,FOR DETAILS SEE P.34-36 2060000100043 OF G.SIMON THESIS. 2060000100044 .CORRECTION FOR OVERLAPPING IN RESONANCES,DETAILS IN 2060000100045 P.32 OF G.SIMON THESIS 2060000100046 .BACKGROUND. 2060000100047 ERR-ANALYS .ONLY STATISTICAL ERRORS ACCOUNTED 2060000100048 ENDBIB 46 0 2060000100049 NOCOMMON 0 0 2060000100050 ENDSUBENT 49 0 2060000199999 SUBENT 20600002 19840126 00002060000200001 BIB 3 7 2060000200002 REACTION (92-U-235(N,F),PR,NU,,RES) PROMPT NU-BAR VALUE AT 2060000200003 PEAK OF RESONANCE. 2060000200004 MONITOR (98-CF-252(0,F),PR,NU) 2060000200005 HISTORY (760729C) 2060000200006 (761217E) 2060000200007 (800523A) G.C., REACTION STRINGS CONVERTED. 2060000200008 (800603E) 2060000200009 ENDBIB 7 0 2060000200010 COMMON 1 3 2060000200011 MONIT 2060000200012 NO-DIM 2060000200013 3.7320E+00 2060000200014 ENDCOMMON 3 0 2060000200015 DATA 3 52 2060000200016 EN-RES DATA DATA-ERR 2060000200017 EV NO-DIM NO-DIM 2060000200018 2.0300E+00 2.4330E+00 7.5000E-02 2060000200019 2.8300E+00 2.4360E+00 6.3000E-02 2060000200020 3.1400E+00 2.4070E+00 3.1000E-02 2060000200021 3.6100E+00 2.4100E+00 1.8000E-02 2060000200022 4.8400E+00 2.4490E+00 4.5000E-02 2060000200023 5.4500E+00 2.4150E+00 3.0000E-02 2060000200024 6.1900E+00 2.4000E+00 2.3000E-02 2060000200025 6.3800E+00 2.3950E+00 1.7000E-02 2060000200026 7.0700E+00 2.4020E+00 1.7000E-02 2060000200027 8.7800E+00 2.4160E+00 6.0000E-03 2060000200028 9.2800E+00 2.4300E+00 1.7000E-02 2060000200029 9.7400E+00 2.4910E+00 3.5000E-02 2060000200030 1.0180E+01 2.4580E+00 2.8000E-02 2060000200031 1.1660E+01 2.3920E+00 2.1000E-02 2060000200032 1.2390E+01 2.3950E+00 8.0000E-03 2060000200033 1.2850E+01 2.4300E+00 3.8000E-02 2060000200034 1.3280E+01 2.3720E+00 4.0000E-02 2060000200035 1.4020E+01 2.4020E+00 1.3000E-02 2060000200036 1.4510E+01 2.3550E+00 3.2000E-02 2060000200037 1.5400E+01 2.4160E+00 2.0000E-02 2060000200038 1.6080E+01 2.3930E+00 2.0000E-02 2060000200039 1.6670E+01 2.3900E+00 1.8000E-02 2060000200040 1.8060E+01 2.4070E+00 1.6000E-02 2060000200041 1.9300E+01 2.3920E+00 7.0000E-03 2060000200042 2.0130E+01 2.5080E+00 4.0000E-02 2060000200043 2.0610E+01 2.4460E+00 3.0000E-02 2060000200044 2.1070E+01 2.4140E+00 1.1000E-02 2060000200045 2.2940E+01 2.4040E+00 2.0000E-02 2060000200046 2.3410E+01 2.3960E+00 3.0000E-02 2060000200047 2.3500E+01 2.4050E+00 1.1000E-02 2060000200048 2.3610E+01 2.4130E+00 2.1000E-02 2060000200049 2.4270E+01 2.4230E+00 3.2000E-02 2060000200050 2.5590E+01 2.3890E+00 2.1000E-02 2060000200051 2.6490E+01 2.3980E+00 1.8000E-02 2060000200052 2.7800E+01 2.3720E+00 1.8000E-02 2060000200053 2.9640E+01 2.2440E+00 6.8000E-02 2060000200054 3.0590E+01 2.4360E+00 4.7000E-02 2060000200055 3.0860E+01 2.3900E+00 4.4000E-02 2060000200056 3.2070E+01 2.4070E+00 1.3000E-02 2060000200057 3.3520E+01 2.4160E+00 1.6000E-02 2060000200058 3.4390E+01 2.4400E+00 1.4000E-02 2060000200059 3.5200E+01 2.4270E+00 1.0000E-02 2060000200060 3.8300E+01 2.4220E+00 3.7000E-02 2060000200061 3.9410E+01 2.3990E+00 1.3000E-02 2060000200062 4.4600E+01 2.3640E+00 2.4000E-02 2060000200063 5.1260E+01 2.4250E+00 1.1000E-02 2060000200064 5.2220E+01 2.4500E+00 1.8000E-02 2060000200065 5.3450E+01 2.4630E+00 3.5000E-02 2060000200066 5.5060E+01 2.4250E+00 1.7000E-02 2060000200067 5.8680E+01 2.3650E+00 2.4000E-02 2060000200068 7.2400E+01 2.4390E+00 2.0000E-02 2060000200069 7.4570E+01 2.3660E+00 2.1000E-02 2060000200070 ENDDATA 54 0 2060000200071 ENDSUBENT 70 0 2060000299999 ENDENTRY 2 0 2060099999999