ENTRY 23235 20140607 22392323500000001 SUBENT 23235001 20140607 22392323500100001 BIB 12 50 2323500100002 REFERENCE (J,JRN,300,609,2014) 2323500100003 #doi:10.1007/s10967-014-3023-3 2323500100004 AUTHOR (C.Chilian,L.Sneyers,P.Vermaercke,G.Kennedy) 2323500100005 TITLE Measurement of k0 and Q0 values for iridium isotopes. 2323500100006 INSTITUTE (2BLGMOL) L.Sneyers,P.Vermaercke. 2323500100007 (1CANMPT) C.Chilian,G.Kennedy. 2323500100008 FACILITY (REAC,2BLGMOL) Irradiation channels S84, Y4 and X26 of 2323500100009 the BR1 reactor at SCK*CEN, Belgium, were used . 2323500100010 INC-SOURCE (REAC) 2323500100011 INC-SPECT Parameters of the neutron spectra: 2323500100012 Channel f a 2323500100013 S84 17.0 -0.003 2323500100014 Y4 38.7 0.066 2323500100015 X26 95.0 0.11 2323500100016 f - ratio of the thermal neutron flux to epithermal 2323500100017 flux, 2323500100018 a - slope parameter of the epithermal spectrum. 2323500100019 METHOD (ACTIV) Ir standards were irradiated under Cd cover and2323500100020 the Cd ratios were subsequently used, along with the 2323500100021 known Q0-values, to determine FCd - resonance neutron 2323500100022 cadmium transmission factor. 2323500100023 The two-channel method was used to determine Q0-values:2323500100024 irradiating a standard of the element, along with Au 2323500100025 monitor, in two reactor irradiation channels with very 2323500100026 different f, to determine the k0-value of one of the 2323500100027 gamma-rays emitted by the nuclide produced. 2323500100028 The Ir foil standards were irradiated in channels S84 2323500100029 and X26. 2323500100030 The specific activities of 192Ir, 194Ir and 198Au were 2323500100031 measured by counting the samples at a distance of 25cm 2323500100032 from the HPGe detector. 2323500100033 The Q0 values obtained were verified using a similar 2323500100034 irradiation in channel Y4. 2323500100035 DETECTOR (HPGE) Gamma-rays were detected with three HPGe 2323500100036 detectors with relative efficiency of about 40 % . 2323500100037 SAMPLE Al-Ir foils were prepared by Central Bureau for Nuclear2323500100038 Measurements (CBNM) by gravimetrically mixing the 2323500100039 components of the alloy; were certified by CBNM to 2323500100040 contain 1.00 +- 0.01 wt% Ir. Discs with 4 mm diameter, 2323500100041 0.1 mm thickness were punched from these foils and 2323500100042 accurately weighed. Each disc contained approximately 2323500100043 33 microg Ir. 2323500100044 The co-irradiated reference standard IRMM 530R Al-Au 2323500100045 foil, containing 0.1003 +- 0.0012 % Au, was punched 2323500100046 similarly. The Au monitors were used to redetermine f 2323500100047 for this work using Cd-ratio measurements. 2323500100048 CORRECTION For coincidence summing < 0.8 %. 2323500100049 For neutron self-shielding using correction factors 2323500100050 calculated by MATSSF and Sigmoid - <0.1%. 2323500100051 HISTORY (20140607C) M.M. 2323500100052 ENDBIB 50 0 2323500100053 COMMON 2 3 2323500100054 EN-MIN-NM EN-MEAN-DN 2323500100055 EV EV 2323500100056 0.5 0.0253 2323500100057 ENDCOMMON 3 0 2323500100058 ENDSUBENT 57 0 2323500199999 SUBENT 23235002 20140607 22392323500200001 BIB 6 20 2323500200002 REACTION ((77-IR-191(N,G)77-IR-192,,RI)// 2323500200003 (77-IR-191(N,G)77-IR-192,,SIG)) 2323500200004 Q0 value (ratio of resonance integral to thermal 2323500200005 neutron activation cross-section) 2323500200006 DECAY-DATA (77-IR-192-G,73.827D,DG,316.) 2323500200007 CORRECTION Epithermal neutron self-shielding was calculated to be 2323500200008 0.55 % (Sigmoid). 2323500200009 ERR-ANALYS (DATA-ERR) The uncertainties include the contributions 2323500200010 from the uncertainties in the measured specific 2323500200011 activities, the effective mean resonance energies, 2323500200012 and f and a of the two irradiation channels used. 2323500200013 1 sigma confidence level. 2323500200014 ADD-RES Measured FCd-value 0.77+-0.02 . 2323500200015 Measured k0-values: 2323500200016 Ir-192 gamma energy K0 Uncertainty,% 2323500200017 295.96 1.13 1.3 2323500200018 308.46 1.17 1.3 2323500200019 316.51 3.23 1.2 2323500200020 468.07 1.85 1.2 2323500200021 STATUS (TABLE) Table 2 of J,JRN,300,609,2014. 2323500200022 ENDBIB 20 0 2323500200023 NOCOMMON 0 0 2323500200024 DATA 2 1 2323500200025 DATA DATA-ERR 2323500200026 NO-DIM NO-DIM 2323500200027 3.47 0.10 2323500200028 ENDDATA 3 0 2323500200029 ENDSUBENT 28 0 2323500299999 SUBENT 23235003 20140607 22392323500300001 BIB 6 21 2323500300002 REACTION ((77-IR-193(N,G)77-IR-194,,RI)// 2323500300003 (77-IR-193(N,G)77-IR-194,,SIG)) 2323500300004 Q0 value (ratio of resonance integral to thermal 2323500300005 neutron activation cross-section) 2323500300006 DECAY-DATA (77-IR-194-G,19.28HR,DG,328.) 2323500300007 CORRECTION Epithermal neutron self-shielding was calculated to be 2323500300008 0.5 % (MATSSF) or 0.59 % (Sigmoid). 2323500300009 ERR-ANALYS (DATA-ERR) The uncertainties include the contributions 2323500300010 from the uncertainties in the measured specific 2323500300011 activities, the effective mean resonance energies, 2323500300012 and f and a of the two irradiation channels used. 2323500300013 1 sigma confidence level. 2323500300014 ADD-RES Measured FCd-value 0.89+-0.02 . 2323500300015 Measured k0-values: 2323500300016 Ir-194 gamma energy K0 Uncertainty,% 2323500300017 293.5 2.01E-02 1.6 2323500300018 328.4 1.04E-01 1.4 2323500300019 645.1 9.42E-03 1.6 2323500300020 938.7 4.72E-03 1.6 2323500300021 1150.8 4.70E-03 1.6 2323500300022 STATUS (TABLE) Table 2 of J,JRN,300,609,2014. 2323500300023 ENDBIB 21 0 2323500300024 NOCOMMON 0 0 2323500300025 DATA 2 1 2323500300026 DATA DATA-ERR 2323500300027 NO-DIM NO-DIM 2323500300028 13.0 0.3 2323500300029 ENDDATA 3 0 2323500300030 ENDSUBENT 29 0 2323500399999 ENDENTRY 3 0 2323599999999