ENTRY 21189 20060809 21782118900000001 SUBENT 21189001 20060809 21782118900100001 BIB 15 54 2118900100002 INSTITUTE (2UK ALD) 2118900100003 REFERENCE (J,JNE/AB,18,561,196410) 2118900100004 AUTHOR (P.RUDDICK,P.H.WHITE) 2118900100005 TITLE -THE MEASUREMENT OF THE NEUTRON FISSION CROSS-SECTION 2118900100006 OF PU-240 IN THE ENERGY RANGE 60-500 KEV- 2118900100007 FACILITY (VDG ) 3 MEV VAN DE GRAAFF. 2118900100008 INC-SOURCE (P-LI7) PROTONS ON LI-F OR LI-N TARGETS. 2118900100009 SAMPLE .THREE PLUTONIUM FOILS USED- 2118900100010 P1. 1.46+-0.01 MG PU-240 WITH ISOTOPIC COMPOSITION 2118900100011 239(6.33 PERCENT),240(93.54 PERCENT),241(0.09 2118900100012 PERCENT),242(0.04 PERCENT). IMPURITY 33 PERCENT 2118900100013 OF TOTAL FOIL WEIGHT. 2118900100014 P2. 1.76+-0.02 MG PU-240 WITH ISOTOPIC COMPOSITION 2118900100015 239(0.27 PERCENT),240(99.28 PERCENT),241(0.29 2118900100016 PERCENT),242(0.16 PERCENT). IMPURITY 13 PERCENT. 2118900100017 P3. 0.896+-0.009 MG PU-240 WITH SAME COMPOSITION AS 2118900100018 P2. IMPURITY CONTENT 35 PERCENT BY WEIGHT. 2118900100019 CHEMICAL IMPURITIES LARGELY COPPER OXIDE. 2118900100020 .TWO URANIUM FOILS FOR NORMALISATION- 2118900100021 U1. 3.309+-0.04 MG URANIUM WITH ISOTOPIC COMPOSITION 2118900100022 234(1.19 PERCENT),235(92.95 PERCENT),236(0.18 2118900100023 PERCENT),238(5.68 PERCENT) BY WEIGHT. IMPURITY 2118900100024 CONTENT LESS THAN 0.7 PERCENT. 2118900100025 U2. 6.797+-0.04 MG URANIUM WITH SAME COMPOSITION AND 2118900100026 IMPURITY CONTENT. 2118900100027 .SAMPLE FOILS LOADED IN GAS SCINTILLATION COUNTER. 2118900100028 METHOD .DETECTION OF FISSION FRAGMENTS. 2118900100029 DETECTOR (SCIN ) GAS SCINTILLATOR FILLED WITH 2/3 ATMOSPHERES 2118900100030 OF XENON THROUGH DRY ICE AND ACETONE TAP. 2118900100031 COUNTER WALLS COATED WITH EVAPORATED AL. 2118900100032 COUNTER VIEWED BY MULLARD 56 AVP PM TUBE. 2118900100033 (LONGC) LONG COUNTER TO MONITOR NEUTRON FLUX. 2118900100034 MONITOR (92-U-235(N,F),,SIG) NORMALISATION TO FISSION CROSS- 2118900100035 SECTIONS OF WHITE 2118900100036 PART-DET (FF) FISSION FRAGMENTS. 2118900100037 CORRECTION .GRAPHICAL CORRECTION FOR FISSION FRAGMENTS LOST BELOW 2118900100038 PILE UP OF ALPHAS FROM PU-240, 1-10 PERCENT OF TOTAL. 2118900100039 .CORRECTION FOR FISSION FRAGMENT ABSORPTION IN FOIL 2118900100040 MATERIAL. 2118900100041 .CONTRIBUTION FROM SPONTANEOUS FISSION IN PU-240 AND 2118900100042 NEUTRON FISSION IN PU-239 AND PU-241. 2118900100043 .NO CORRECTION FOR FISSION INDUCED BY NEUTRONS 2118900100044 SCATTERED FROM FLOOR, WALLS AND COUNTER MATERIALS. 2118900100045 .COUNTING RATE FROM PHOTO-FISSION ESTIMATED TO BE 2118900100046 SMALL. 2118900100047 ERR-ANALYS .ERRORS ARE STANDARD DEVIATIONS AND ARE MAINLY DUE TO 2118900100048 COUNTING STATISTICS, SUBTACTION OF SPONTANEOUS 2118900100049 FISSION CONTRIBUTION AND UNCERTAINTY IN GRAPHICAL 2118900100050 EXTRAPOLATION OF FISSION FRAGMENT SPECTRUM BELOW 2118900100051 ALPHA PILE UP. 2118900100052 STATUS (NDD) FROM NEUDADA. 2118900100053 HISTORY (19791121T) 2118900100054 (19800110E) 2118900100055 (20060809A) DATE and reference code corrected 2118900100056 ENDBIB 54 0 2118900100057 NOCOMMON 0 0 2118900100058 ENDSUBENT 57 0 2118900199999 SUBENT 21189002 20060809 21782118900200001 BIB 4 8 2118900200002 REACTION (94-PU-240(N,F),,SIG) 2118900200003 FLAG (1.) FOILS U1 AND P3. 2118900200004 (2.) FOILS U1 AND P2. 2118900200005 (3.) FOILS U2 AND P1. 2118900200006 REFER TO NUMBER OF PU-240 SAMPLE FOIL AND U-235 2118900200007 NORMALISATION FOIL. 2118900200008 STATUS .TABLE 1 OF THE PUBLICATION. 2118900200009 HISTORY (20060809U) COLUMN ORDER CORRECTED 2118900200010 ENDBIB 8 0 2118900200011 NOCOMMON 0 0 2118900200012 DATA 6 13 2118900200013 EN EN-RSL DATA DATA-ERR MONIT FLAG 2118900200014 KEV KEV MB MB B NO-DIM 2118900200015 6.1000E+01 1.5000E+01 1.0000E+02 2.0000E+01 1.9200E+00 1.0000E+002118900200016 7.6000E+01 3.0000E+01 5.9000E+01 1.5000E+01 1.8000E+00 2.0000E+002118900200017 7.9000E+01 1.5000E+01 6.1000E+01 1.4000E+01 1.7700E+00 1.0000E+002118900200018 1.0500E+02 1.5000E+01 8.2000E+01 1.5000E+01 1.6300E+00 1.0000E+002118900200019 1.2400E+02 1.2000E+01 7.1000E+01 2.4000E+01 1.5600E+00 1.0000E+002118900200020 1.4500E+02 1.8000E+01 9.8000E+01 1.9000E+01 1.5000E+00 2.0000E+002118900200021 1.5600E+02 2.5000E+01 5.8000E+01 3.6000E+01 1.4700E+00 3.0000E+002118900200022 2.9500E+02 2.0000E+01 1.2700E+02 2.7000E+01 1.2800E+00 2.0000E+002118900200023 3.7900E+02 6.0000E+00 1.9200E+02 3.6000E+01 1.2100E+00 1.0000E+002118900200024 4.1300E+02 2.0000E+01 2.0100E+02 3.0000E+01 1.2000E+00 2.0000E+002118900200025 4.3000E+02 6.0000E+00 2.3900E+02 4.5000E+01 1.1900E+00 1.0000E+002118900200026 4.5800E+02 1.5000E+01 2.6200E+02 6.2000E+01 1.1800E+00 3.0000E+002118900200027 4.8500E+02 2.5000E+01 2.8500E+02 5.4000E+01 1.1700E+00 2.0000E+002118900200028 ENDDATA 15 0 2118900200029 ENDSUBENT 28 0 2118900299999 ENDENTRY 2 0 2118999999999