ENTRY 30683 20090904 31403068300000001 SUBENT 30683001 20090904 31403068300100001 BIB 14 29 3068300100002 INSTITUTE (3ARGCNE) 3068300100003 REFERENCE (J,RCA,34,157,1983) 3068300100004 AUTHOR (I.M.Cohen,C.Magnavacca,G.B.Baro) 3068300100005 TITLE Some reaction cross-sections for molybdenum in a 3068300100006 fission spectrum 3068300100007 FACILITY (REAC,3ARGCNE) RA-3 reactor with a fast flux of 3068300100008 1.1x10**13 n/cm2/s. 3068300100009 INC-SPECT Fast neutron component of the reactor RA-3 is very 3068300100010 similar to a fission spectrum 3068300100011 SAMPLE High purity metal foils placed in small cadmium box 3068300100012 METHOD (ACTIV) 3068300100013 DETECTOR (GELI) 70 cm3 with a 2.4 keV resolution for the 3068300100014 1332.5 keV peak of Co-60 3068300100015 MONITOR ((MONIT1)26-FE-54(N,P)25-MN-54,,SIG) 3068300100016 ((MONIT2)25-MN-55(N,2N)25-MN-54,,SIG) 3068300100017 MONIT-REF (,A.CALAMAND,R,IAEA-156,1974) for both reactions 3068300100018 ERR-ANALYS (DATA-ERR) The indicated uncertainties include: 3068300100019 -Statistical dispersion of the average of three 3068300100020 independent measurements 3068300100021 -Certified and measurement error of the Mn-54 standard 3068300100022 source used to normalize relative efficiency values 3068300100023 into absolute ones 3068300100024 -Errors of standard reaction cross sections 3068300100025 -Errors of the measured radiation intensities 3068300100026 STATUS (TABLE) Data taken from Radiochimica 3068300100027 Acta,34(1983)157, Table 3.3068300100028 HISTORY (19840828C) DG.- 3068300100029 (20090725A) SD:Updated to new date formats,lower case. 3068300100030 OS. Changed SF8 to FIS in all subents. 3068300100031 ENDBIB 29 0 3068300100032 COMMON 5 3 3068300100033 EN-DUMMY MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 3068300100034 MEV MB MB MB MB 3068300100035 1.5000E+00 8.2500E+01 5.0000E+00 2.5800E-01 1.3000E-02 3068300100036 ENDCOMMON 3 0 3068300100037 ENDSUBENT 36 0 3068300199999 SUBENT 30683002 20090904 31403068300200001 BIB 2 2 3068300200002 REACTION (42-MO-92(N,P)41-NB-92-M,,SIG,,FIS) 3068300200003 DECAY-DATA (41-NB-92-M,10.15D,DG,934.0,0.992) 3068300200004 ENDBIB 2 0 3068300200005 NOCOMMON 0 0 3068300200006 DATA 2 1 3068300200007 DATA DATA-ERR 3068300200008 MB MB 3068300200009 6.9200E+00 4.3000E-01 3068300200010 ENDDATA 3 0 3068300200011 ENDSUBENT 10 0 3068300299999 SUBENT 30683003 20090904 31403068300300001 BIB 3 10 3068300300002 REACTION (42-MO-92(N,2N)42-MO-91-M,,SIG,,FIS) 3068300300003 DECAY-DATA (41-NB-91-M,62.D,DG,1205.0,0.034) 3068300300004 one of the Mo-91-m daughters 3068300300005 COMMENT Author comment.- There is a possibility that some of 3068300300006 the Nb-91-m measured could have originated via 3068300300007 Mo-92((n,np)+(n,pn))Nb-91-m reactions. The present 3068300300008 cross section value is useful in order to predict 3068300300009 the activity of Nb-91-m formed by irradiation of 3068300300010 natural Mo with reactor neutrons, being the upper 3068300300011 limit for the cross section of Mo-92(n,2n)Mo-91-m.- 3068300300012 ENDBIB 10 0 3068300300013 NOCOMMON 0 0 3068300300014 DATA 2 1 3068300300015 DATA-MAX DATA-ERR 3068300300016 MB MB 3068300300017 7.5100E-02 5.3000E-03 3068300300018 ENDDATA 3 0 3068300300019 ENDSUBENT 18 0 3068300399999 SUBENT 30683004 20090904 31403068300400001 BIB 3 4 3068300400002 REACTION (42-MO-95(N,P)41-NB-95,,SIG,,FIS) 3068300400003 DECAY-DATA (41-NB-95,35.15D,DG,765.6,0.998) 3068300400004 CORRECTION Corrected for contribution by decay of Zr-95 3068300400005 formed by Mo-98(n,alpha)Zr-95 reaction 3068300400006 ENDBIB 4 0 3068300400007 NOCOMMON 0 0 3068300400008 DATA 2 1 3068300400009 DATA DATA-ERR 3068300400010 MB MB 3068300400011 1.5110E-01 9.1000E-03 3068300400012 ENDDATA 3 0 3068300400013 ENDSUBENT 12 0 3068300499999 SUBENT 30683005 20090904 31403068300500001 BIB 2 2 3068300500002 REACTION (42-MO-98(N,A)40-ZR-95,,SIG,,FIS) 3068300500003 DECAY-DATA (40-ZR-95,64.0D,DG,756.5,0.546) 3068300500004 ENDBIB 2 0 3068300500005 NOCOMMON 0 0 3068300500006 DATA 2 1 3068300500007 DATA DATA-ERR 3068300500008 MB MB 3068300500009 8.5700E-03 5.6000E-04 3068300500010 ENDDATA 3 0 3068300500011 ENDSUBENT 10 0 3068300599999 ENDENTRY 5 0 3068399999999