ENTRY 22085 19900905 00002208500000001 SUBENT 22085001 19900905 00002208500100001 BIB 14 59 2208500100002 REFERENCE (C,88MITO,1057,88) MAIN REFERENCE, UPDATED RESULTS. 2208500100003 (C,85SANTA,1,521,85) PRELIMINARY RESULTS. 2208500100004 (J,RE,93,185,86) SAME AS 85SANTA. 2208500100005 (R,AERE-R-12612,8705) FULL EXPERIMENTAL DETAILS. 2208500100006 TITLE -A MEASUREMENT OF THE NB-93(N,INL)NB-93-M CROSS-SECTION2208500100007 IN THE ENERGY RANGE 1 TO 6 MEV. 2208500100008 AUTHOR (D.B.GAYTHER,C.A.UTTLEY,M.F.MURPHY,W.H.TAYLOR,K.RANDLE)2208500100009 INSTITUTE (2UK HAR) D.B.G AND C.A.U. AND EXPERIMENTAL SITE. 2208500100010 (2UK BIR) K.R. AND EXPERIMENTAL SITE. 2208500100011 (2UK WIN) M.F.M AND W.H.T. 2208500100012 FACILITY (VDG) HARWELL 5 MV VAN DE GRAAFF ACCELERATOR, USED AT 2208500100013 2.7 MEV NEUTRON ENERGY. 2208500100014 (DYNAM) 3 MV DYNAMITRON OF BIRMINGHAM UNIVERSITY 2208500100015 RADIATION CENTRE, USED AT THE OTHER ENERGIES. 2208500100016 INC-SOURCE (P-T) USED FOR NEUTRON ENERGIES 1 - 2.7 MEV. 2208500100017 (D-D) USED FOR NEUTRON ENERGIES 2.8 - 6 MEV. 2208500100018 THE NEUTRON FLUENCES WERE IN THE RANGE 5.0E+12 TO 2208500100019 2.4E+13 N/CM2. 2208500100020 METHOD (ACTIV) 2208500100021 DETECTOR (FISCH) A FISSION IONISATION CHAMBER, WITH A DEPOSIT OF2208500100022 95.1 +/- 0.5 MICROGRAMS OF 99.94 PERCENT U-235 PAINTED2208500100023 ON A 0.127 MM PLATINUM PLATE LOCATED INSIDE THE SUR- 2208500100024 FACE OF THE CHAMBER WALL, WAS USED TO DETERMINE THE 2208500100025 NEUTRON FLUENCE. THE DEPOSIT HAD THE SAME DIAMETER AS 2208500100026 THE NIOBIUM FOIL. 2208500100027 (HPGE) AN INTRINSIC GERMANIUM X-RAY SPECTROMETER WAS 2208500100028 USED TO MEASURE THE ACTIVITY OF THE FOILS. THE DETEC- 2208500100029 TOR WAS EFFICIENCY CALIBRATED WITH A STANDARD SOLUTION2208500100030 OF NB-93-M. 2208500100031 MONITOR (92-U-235(N,F),,SIG) FISSION CHAMBER. 2208500100032 SAMPLE .NIOBIUM METAL FOIL SAMPLES, PLACED AT ABOUT 20 MM FROM2208500100033 THE NEUTRON SOURCE DURING IRRADIATIONS. ALSO FOILS OF 2208500100034 NI-58, U-235 AND U-238 WERE USED TO DETERMINE THE 2208500100035 NEUTRON FLUENCE AND AND LOW ENERGY BACKGROUND 2208500100036 NEUTRONS. THE SAMPLES WERE PACKED AS MULTI-LAYER SAND-2208500100037 WICHES. 2208500100038 CORRECTION .THE DATA WERE CORRECTED FOR FRAGMENT ABSORPTION IN THE2208500100039 FISSILE DEPOSIT AND LOSS OF EVENTS BELOW THE PULSE 2208500100040 HEIGHT DISCRIMINATION LEVEL OF THE FISSION CHAMBER. 2208500100041 ERR-ANALYS (DATA-ERR) THE UNCERTAINTIES WERE COMPOSED OF THE 2208500100042 FOLLOWING CONTRIBUTIONS 2208500100043 X 2208500100044 ERROR SOURCE ERROR, PERCENT 2208500100045 X 2208500100046 MASS OF U-235 0.5 2208500100047 MASS OF NB-93 0.2 2208500100048 U-235(N,F) CROSS SECTION 1.0 2208500100049 NB-93-M ACTIVITY 2.0 - 7.0 2208500100050 NB-93-M HALF-LIFE 0.9 2208500100051 NUMBER OF FISSION EVENTS 0.2 - 0.4 2208500100052 GEOMETRY EFFECT 2.0 2208500100053 X 2208500100054 STATUS .DATA TAKEN FROM MAIN REF. 2208500100055 HISTORY (881128C) N.O. 2208500100056 (881216E) 2208500100057 (890530U) IF. PAGE ADDED TO THE REFERENCE 2208500100058 (890919E) 2208500100059 (900905U) S.W. FURTHER REFERENCES ADDED. 2208500100060 (900917E) 2208500100061 ENDBIB 59 0 2208500100062 NOCOMMON 0 0 2208500100063 ENDSUBENT 62 0 2208500199999 SUBENT 22085002 19881216 00002208500200001 BIB 4 5 2208500200002 REACTION (41-NB-93(N,INL)41-NB-93-M,,SIG) 2208500200003 DECAY-DATA (41-NB-93-M,16.13YR,XR,16.6) 2208500200004 STATUS .DATA TAKEN FROM MAIN REF. 2208500200005 HISTORY (881128C) N.O. 2208500200006 (881216E) 2208500200007 ENDBIB 5 0 2208500200008 NOCOMMON 0 0 2208500200009 DATA 4 10 2208500200010 EN EN-RSL DATA DATA-ERR 2208500200011 MEV MEV MB PER-CENT 2208500200012 1.0900E+00 1.9000E-01 7.4800E+01 4.5000E+00 2208500200013 2.1000E+00 1.4000E-01 2.0100E+02 3.9000E+00 2208500200014 2.7000E+00 2.0000E-01 2.4550E+02 3.3000E+00 2208500200015 3.2900E+00 3.6000E-01 2.5550E+02 5.1000E+00 2208500200016 3.7300E+00 3.4000E-01 2.7420E+02 3.7000E+00 2208500200017 4.0300E+00 1.4000E-01 2.6150E+02 7.7000E+00 2208500200018 4.4500E+00 2.7000E-01 2.5130E+02 3.7000E+00 2208500200019 5.0500E+00 2.5000E-01 2.8020E+02 4.3000E+00 2208500200020 5.5300E+00 1.8000E-01 2.5100E+02 4.1000E+00 2208500200021 5.7600E+00 1.8000E-01 2.3150E+02 4.6000E+00 2208500200022 ENDDATA 12 0 2208500200023 ENDSUBENT 22 0 2208500299999 ENDENTRY 2 0 2208599999999