ENTRY 21190 20060809 21782119000000001 SUBENT 21190001 20060809 21782119000100001 BIB 15 48 2119000100002 INSTITUTE (2UK ALD) 2119000100003 REFERENCE (J,JNE/AB,19,325,196505) 2119000100004 AUTHOR (P.H.WHITE) 2119000100005 TITLE -MEASUREMENTS OF THE U-235 NEUTRON FISSION CROSS- 2119000100006 SECTION IN THE ENERGY RANGE 0.04-14 MEV- 2119000100007 FACILITY (VDG ) VAN DE GRAAFF. 2119000100008 INC-SOURCE (P-LI7) 40-500 KEV. 2119000100009 (P-T) 1.0 AND 2.25 MEV. 2119000100010 (D-D ) 5 MEV. 2119000100011 (D-T ) 14.1 MEV. 2119000100012 SAMPLE .TWO URANIUM SAMPLES USED- 2119000100013 SAMPLE 1, ISOTOPIC COMPOSITION U-235(.9295),U-234 2119000100014 (.0119),U-236(.00179),U-238(.0568) AND CHEMICAL 2119000100015 PURITY 99.98 PERCENT. 2119000100016 SAMPLE 2, ISOTOPIC COMPOSITION U-235(.9933),U-234 2119000100017 (.00116),U-236(.00248),U-238(.00311), CHEMICAL 2119000100018 PURITY UNKNOWN. 2119000100019 METHOD .DETECTION OF FISSION FRAGMENTS. 2119000100020 DETECTOR (FISCH) FISSION CHAMBER FILLED WITH MIXTURE OF 90 2119000100021 PERCENT XENON AND 10 PERCENT CO2. 2119000100022 (PROPC) PROTON RECOIL PROPORTIONAL COUNTER FOR FLUX 2119000100023 MEASUREMENT. COUNTER FILLED WITH HYDROGEN GAS 2119000100024 FOR THE RANGE 40-500 KEV, METHANE GAS FOR THE 2119000100025 RANGE 500 KEV-2.25 MEV. 2119000100026 MONITOR (1-H-1(N,EL)1-H-1,,SIG) NORMALIZATION TO EXPERIMENTAL 2119000100027 N-P CROSS-SECTION EXCEPT IN THE RANGE 0.002- 2119000100028 1 MEV WHERE THE THEORETICAL CURVE WAS USED. 2119000100029 PART-DET (FF) FISSION FRAGMENTS. 2119000100030 CORRECTION .CORRECTION FOR LOSS OF FISSION FRAGMENTS IN THE 2119000100031 THICKNESS OF THE FOIL BY COMPARING FOILS OF 2119000100032 DIFFERENT THICKNESS. 2119000100033 .NO CORRECTION MADE FOR BACKSCATTERING OF FISSION 2119000100034 FRAGMENTS. 2119000100035 .CORRECTION FOR SPATIALLY CONSTANT NEUTRON BACKGROUND 2119000100036 BY INVERSE SQUARE PLOT OF COUNTING RATE AT VARIOUS 2119000100037 DISTANCES FROM THE SOURCE. 2119000100038 .ATTENUATION IN AIR AND SCATTERING FROM TARGET AND 2119000100039 COUNTER STRUCTURES CALCULATED NUMERICALLY AND 2119000100040 AMOUNTED TO 1-4 PERCENT. 2119000100041 .BACKGROUND OF NEUTRONS GENERATED FROM THE TARGET 2119000100042 STRUCTURE MEASURED BY REMOVAL OF TARGET MATERIAL. 2119000100043 EFFECT LESS THAN 2 PERCENT EXCEPT FOR FISSION CHAMBER 2119000100044 WITH D-D SOURCE WHERE BACKGROUND WAS 30 PERCENT. 2119000100045 ERR-ANALYS .COMPREHENSIVE BREAKDOWN OF ERRORS GIVEN AT 150 KEV. 2119000100046 STATUS (NDD) FROM NEUDADA. 2119000100047 HISTORY (19791121C) 2119000100048 (19800110E) 2119000100049 (20060809A) DATE and reference code corrected 2119000100050 ENDBIB 48 0 2119000100051 NOCOMMON 0 0 2119000100052 ENDSUBENT 51 0 2119000199999 SUBENT 21190002 20060809 21782119000200001 BIB 3 12 2119000200002 REACTION (92-U-235(N,F),,SIG) 2119000200003 FLAG (1.) H2 GAS RECOIL COUNTER. 2119000200004 (2.) AVERAGE OF MEASUREMENTS USING H2 AND CH4 RECOIL 2119000200005 COUNTERS. 2119000200006 (3.) CH4 RECOIL COUNTER. 2119000200007 (4.) AVERAGE OF MEASUREMENTS USING CH4 AND SEMI- 2119000200008 CONDUCTOR RECOIL COUNTERS. 2119000200009 (5.) SEMICONDUCTOR RECOIL COUNTER. 2119000200010 (6.) ALPHA YIELD FROM D-T REACTION AT 84 OR 135 2119000200011 DEGREES. 2119000200012 ALL FLAGS GIVE METHOD OF FLUX MONITORING. 2119000200013 STATUS .TABLE 3 OF THE PUBLICATION. 2119000200014 ENDBIB 12 0 2119000200015 NOCOMMON 0 0 2119000200016 DATA 6 12 2119000200017 EN EN-RSL DATA DATA-ERR MONIT FLAG 2119000200018 MEV MEV B PER-CENT B NO-DIM 2119000200019 4.0000E-02 4.0000E-03 2.1000E+00 3.0000E+00 1.6300E+01 1.0000E+002119000200020 6.7000E-02 5.0000E-03 1.7860E+00 3.0000E+00 1.4460E+01 1.0000E+002119000200021 1.2700E-01 1.5000E-02 1.5400E+00 2.5000E+00 1.1730E+01 1.0000E+002119000200022 1.6000E-01 2.0000E-02 1.5200E+00 2.5000E+00 1.0670E+01 1.0000E+002119000200023 2.0700E-01 2.0000E-02 1.3800E+00 2.5000E+00 9.5500E+00 1.0000E+002119000200024 3.1200E-01 2.0000E-02 1.3000E+00 2.5000E+00 7.8900E+00 1.0000E+002119000200025 4.0400E-01 2.0000E-02 1.2200E+00 2.5000E+00 6.8500E+00 1.0000E+002119000200026 5.0500E-01 2.0000E-02 1.1700E+00 2.5000E+00 6.1300E+00 2.0000E+002119000200027 1.0000E+00 5.0000E-02 1.2200E+00 2.5000E+00 4.2600E+00 3.0000E+002119000200028 2.2500E+00 5.0000E-02 1.3100E+00 3.0000E+00 2.7000E+00 4.0000E+002119000200029 5.4000E+00 1.0000E-01 1.0000E+00 5.0000E+00 1.5500E+00 5.0000E+002119000200030 1.4100E+01 5.0000E-02 2.1700E+00 2.0000E+00 6.8900E-01 6.0000E+002119000200031 ENDDATA 14 0 2119000200032 ENDSUBENT 31 0 2119000299999 ENDENTRY 2 0 2119099999999