ENTRY 21901 19860703 00002190100000001 SUBENT 21901001 19860703 00002190100100001 BIB 17 58 2190100100002 INSTITUTE (2GERKIG) H.-U.F EXPERIMENTAL SITE. 2190100100003 (3BZLUFP) J.L.BF 2190100100004 REFERENCE (R,GKSS-81-E-53,81) 2190100100005 AUTHOR (J.L.BARREIRA FILHO,H.-U.FANGER) 2190100100006 TITLE -CROSS-SECTION DETERMINATION FOR THE TI-50(N,P)SC-50 2190100100007 REACTION IN THE 14 MEV NEUTRON ENERGY REGION- 2190100100008 FACILITY .NEUTRON GENERATOR IN A FACILITY CALLED 'KORONA', 2190100100009 KOMBINIERTE ROHRPOST-NEUTRONENGENERATOR-ANLAGE. 2190100100010 INC-SOURCE (D-T ) THE NEUTRON FLUX AT THE IRRADIATION POSITION 2190100100011 WAS ESTIMATED TO 5*10E+10 N/CM-SQ*SEC. 2190100100012 SAMPLE .ALL SAMPLES WERE PREPARED FROM POWDER OXIDE,99.0 PER 2190100100013 CENT PURITY, WITH THE EXCEPTION OF NIOBIUM WHICH 2190100100014 CONSISTED OF METALLIC POWDER, 99.9 PER CENT PURITY. 2190100100015 THE IRRADIATION CAPSULES WERE MADE OF POLYETHYLENE 2190100100016 MATERIAL WITH A DIAMETER OF 1.40 CM AND A HEIGHT OF 2190100100017 0.90 CM. 2190100100018 METHOD (ACTIV) CYCLIC ACTIVATION ANALYSIS WHICH MEANS THAT 2190100100019 THERE IS A CLOSE CYCLE OF ANALYSIS AND RETURN OF THE 2190100100020 SAMPLE IN THE IRRADIATION POSITION, REPEATED SEVERAL 2190100100021 TIMES. 2190100100022 DETECTOR (GELI ) GELI DETECTOR. 2190100100023 ANALYSIS .THE EFFICIENCY OF THE DETECTION SYSTEM WAS MADE WITH A2190100100024 STANDARD RADIOACTIV SOLUTION IN A SAMPLE CAPSULE. 2190100100025 MONITOR .THE NEUTRON FLUX WAS MONITORED BY MEANS OF A BF3 TUBE 2190100100026 IN A LONG COUNTER WHICH WAS CALIBRATED WITH THE REACT.2190100100027 1(41-NB-93(N,2N)41-NB-92-M,,SIG) FOR FLUX MEASURM. AND 2190100100028 2(40-ZR-90(N,2N)40-ZR-89-G,IND/M+,SIG) FOR DETERMINATION2190100100029 OF THE NEUTRON ENERGY. FOR THE FIRST REACTION A CROSS 2190100100030 SECTION FROM NETHAWAY,JIN,40,1285(1978) WAS USED 2190100100031 GIVING A NEUTRON FLUX CORRESPONDING TO A CROSS SECTION2190100100032 FOR THE SECOND REACTION OF (724+-73) MB WHICH 2190100100033 ACCORDING TO THE CROSS-SECTION VARIATION OF THAT 2190100100034 REACTION GAVE THE NEUTRON ENERGY (14.4+-0.3) MEV. 2190100100035 THE CALIBRATION FACTOR WAS ALSO MEASURED WITH 2190100100036 3(13-AL-27(N,A)11-NA-24,,SIG) 2190100100037 DECAY-MON 1(41-NB-92-M,10.15D,DG,934.53,.992) 2190100100038 2(40-ZR-89-G,78.43HR,DG,909.20,.999) 2190100100039 3(11-NA-24,15.02HR,DG,1368.63,1.000,DG,2754.10,.999) 2190100100040 PART-DET (DG ) DECAY GAMMAS. 2190100100041 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2190100100042 HISTORY (840510C) A.L. 2190100100043 (840710E) 2190100100044 (860324U)N.CH 2190100100045 (860416E) 2190100100046 (860620U)HH N2 IN COMMON CHANGED TO 6 2190100100047 (860703E) 2190100100048 CORRECTION .RECORDED GAMMA SPECTRA WERE CORRECTED FOR COINCIDENCE 2190100100049 SUMMING OF CASCADING PHOTONS. DUE TO THE CLOSE 2190100100050 GEOMETRY THIS CORRECTION SOMETIMES (SC-50) AMOUNTED TO2190100100051 AS MUCH AS 20 PER CENT. 2190100100052 ERR-ANALYS (DATA-ERR) TOTAL ERROR UNDER MOST ADVERS CONDITIONS, 2190100100053 BEING A SUM OF 2190100100054 (DATA-ERR1) ERROR IN FLUX DETERMINATION 2190100100055 (DATA-ERR2) ERROR IN GAMMA-RAY YIELD COMPRISING 2190100100056 UNSERTAINTIES IN PHOTOPEAK COUNTS, THE 2190100100057 EFFICIENCY AND GAMMA-TRANSITION INTENSITIES2190100100058 (DATA-ERR3) ERROR IN COINCIDENCE SUMMING CORRECTIONS 2190100100059 (DATA-ERR4) ERRORS IN OTHER PARAMETERS. 2190100100060 ENDBIB 58 0 2190100100061 COMMON 8 6 2190100100062 EN EN-ERR MONIT 3MONIT-ERR 3DATA-ERR1 DATA-ERR2 2190100100063 DATA-ERR3 DATA-ERR4 2190100100064 MEV MEV MB MB PER-CENT PER-CENT 2190100100065 PER-CENT PER-CENT 2190100100066 1.4400E+01 3.0000E-01 1.1700E+02 8.0000E-01 5.0000E+00 6.0000E+002190100100067 2.0000E+00 2.0000E+00 2190100100068 ENDCOMMON 6 0 2190100100069 ENDSUBENT 68 0 2190100199999 SUBENT 21901002 19860321 00002190100200001 BIB 4 8 2190100200002 REACTION (22-TI-50(N,P)21-SC-50,,SIG) 2190100200003 DECAY-DATA (21-SC-50,1.71MIN,DG,523.50,.88,DG,1121.03,1.000, 2190100200004 DG,1553.71,1.000) 2190100200005 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2190100200006 HISTORY (840510C) A.L. 2190100200007 (840710E) 2190100200008 (860321A)N.CH 2190100200009 (860416E) 2190100200010 ENDBIB 8 0 2190100200011 NOCOMMON 0 0 2190100200012 DATA 2 1 2190100200013 DATA DATA-ERR 2190100200014 MB MB 2190100200015 1.4300E+01 2.1000E+00 2190100200016 ENDDATA 3 0 2190100200017 ENDSUBENT 16 0 2190100299999 ENDENTRY 2 0 2190199999999