ENTRY 21719 19810723 00002171900000001 SUBENT 21719001 19810723 00002171900100001 BIB 15 47 2171900100002 INSTITUTE (2BLGGHT) INSTITUTE FOR NUCLEAR SCIENCES, UNIV OF GHENT2171900100003 (2BLGMOL) REACTOR SITE. 2171900100004 REFERENCE (J,JIN,35,(2),381,7302) FULL REPORT. 2171900100005 (T,FRANCOIS,,73) THESIS, UNIV OF GHENT. 2171900100006 AUTHOR (J.P.FRANCOIS,R.GIJBELS,J.HOSTE) 2171900100007 TITLE -THE AVERAGE CROSS SECTION OF THE MN-55(N,2N) REACTION 2171900100008 IN A FISSION NEUTRON SPECTRUM -. 2171900100009 FACILITY (REAC ) BR-2 REACTOR, S.C.K. MOL. 2171900100010 INC-SOURCE (REAC ) THERMAL FLUX OF 1.76 10**14 N/CM2/SEC 2171900100011 DETEMINED BY COBALT AND SILVER MONITORS. 2171900100012 INC-SPECT .THE EQUIVALENT FISSION SPECTRUM FLUX WAS 2171900100013 MEASURED USING THE FOLLOWING THRESHOLD REACTIONS.. 2171900100014 S-32(N,P),NI-58(N,P),FE-54(N,P),AL-27(N,A) AND 2171900100015 NI-58(N,2N). THE RATIO OF THERMAL TO EPITHERMAL FLUXE 2171900100016 WAS FOUND TO BE 23.7 . EQUIVALENT FISSION FLUXES 2171900100017 DERIVED FROM MEASUREMENTS WITH THE FIVE THRESHOLD 2171900100018 REACTION MONITORS VARIED BY 17 PERCENT, BUT WITHOUT 2171900100019 ANY SYSTEMATIC TREND WITH THRESHOLD ENERGY. 2171900100020 SAMPLE .TWO SPEC PURE MN3 O4 SAMPLES OF 11.52 AND 12.20 GM 2171900100021 WERE IRRADIATED IN A STANDARD GRAPHITE CONTAINER, 5.4 2171900100022 CM HIGH AND 1.9 CM DIAMETER. ALL SAMPLES WERE PACKED 2171900100023 IN QUARTZ TUBES AND IRRADIATED FOR 15 HOURS. 2171900100024 THE MANGANESE CONTENT OF THE SAMPLES WAS DETERMINED BY2171900100025 POTENTIOMETRIC TITRATION IN A PYROPHOSPHATE SOLUTION 2171900100026 AND BY PRECISION SPECTROPHOTOMETRY. THE MEAN VALUE WAS2171900100027 71.3 PERCENT COMPARED WITH A THEORETICAL VALUE OF 72.02171900100028 PERCENT. 2171900100029 METHOD (ACTIV) ACTIVATION. MEASUREMENT OF THE 303 DAY MN-54 2171900100030 ACTIVITY. 2171900100031 DETECTOR (GELI ) GE(LI) DETECTOR. 2171900100032 MONITOR (13-AL-27(N,A)11-NA-24,,SIG,,FIS) VALUE TAKEN AS 0.60MB2171900100033 OTHER MONITORS WERE USED WITH ADOPTED CROSS SECTION 2171900100034 VALUES OF ... S-32(N,P) 65 MB 2171900100035 NI-58(N,P) 102 MB 2171900100036 FE-54(N,P) 66 MB 2171900100037 NI-58(N,2N) 0.004 MB 2171900100038 STATUS .TEXT, PAGE 387. 2171900100039 HISTORY (810109C) 2171900100040 (810120E) 2171900100041 CORRECTION .THE NI-58(N,P) MONITOR VALUES WERE CORRECTED FOR 2171900100042 BURN-UP OF THE CO-58 PRODUCT USING THE KNOWN THERMAL 2171900100043 NEUTRON FLUX. 2171900100044 MANGANESE SAMPLES WERE CHECKED FOR FE-54 IMPURITIES 2171900100045 AND NO INTERFERING ACTIVITY WAS FOUND. 2171900100046 ERR-ANALYS .UNCERTAINTY ESTIMATED BY COMPILOR AS 17 PERCENT, 2171900100047 REPRESENTING THE SPREAD IN EFFECTIVE FISSION FLUXES 2171900100048 FROM THE FIVE MONITORS. 2171900100049 ENDBIB 47 0 2171900100050 COMMON 2 3 2171900100051 EN-DUMMY MONIT 2171900100052 MEV MB 2171900100053 1.5000E+00 6.0000E-01 2171900100054 ENDCOMMON 3 0 2171900100055 ENDSUBENT 54 0 2171900199999 SUBENT 21719002 19810120 00002171900200001 BIB 4 6 2171900200002 REACTION (25-MN-55(N,2N)25-MN-54,,SIG,,FIS) FISSION SPECTRUM 2171900200003 AVERAGE CROSS SECTION. 2171900200004 DECAY-DATA (25-MN-54,303.D,DG,834.9) 2171900200005 STATUS .TEXT, PAGE 387. 2171900200006 HISTORY (810109C) 2171900200007 (810120E) 2171900200008 ENDBIB 6 0 2171900200009 NOCOMMON 0 0 2171900200010 DATA 2 1 2171900200011 DATA DATA-ERR 2171900200012 MB PER-CENT 2171900200013 2.1000E-01 1.7000E+01 2171900200014 ENDDATA 3 0 2171900200015 ENDSUBENT 14 0 2171900299999 ENDENTRY 2 0 2171999999999