ENTRY 21891 20230208 231321891 0 1 SUBENT 21891001 20230208 231321891 1 1 BIB 15 48 21891 1 2 TITLE Measurement of neutron activation cross 21891 1 3 sections by generalized intermittent radiation 21891 1 4 AUTHOR (D.Antonini,P.Moioli,E.Pedretti,R.Scafe,A.Visentin) 21891 1 5 REFERENCE (J,NIM,151,567,1978) 21891 1 6 INSTITUTE (2ITYCAS) 21891 1 7 FACILITY (REAC,2ITYCAS) TRIGA reactor 21891 1 8 INC-SOURCE (REAC) 21891 1 9 INC-SPECT Thermal neutron flux between 21891 1 10 1. and 17. * 10**9 neutrons/S*cm**2. 21891 1 11 SAMPLE Foils enclosed in a small aluminum capsule, 21891 1 12 rigidly positioned within a cylindrical nylon 21891 1 13 container (length 10 cm, diameter 2 cm) used 21891 1 14 as a 'RABBIT'. 21891 1 15 Au-foil, 1% Au and 99% Al, 21891 1 16 diam 10 mm, thickn. 0.1 mm, mass 20 mg. 21891 1 17 In-foil 1, 100% in, 21891 1 18 diam 1.5 mm, thickn. 0.18 mm, mass 2.25 mg 21891 1 19 in-foil 2, 0.7% in, 99.3% Pb, 21891 1 20 diam 3 mm, thickn. 0.19 mm, mass 15 mg. 21891 1 21 METHOD (ACTIV) Activation was done in intermittent 21891 1 22 irradiations by rapidly inserting the sample into 21891 1 23 a triga reactor core and by rapidly withdrawing it 21891 1 24 while the neutron flux in the core was changed. 21891 1 25 Neutron flux during irradiations was measured with 21891 1 26 a gamma-compensated ionization chamber. Several 21891 1 27 patterns of intermittent irradiations were tested. 21891 1 28 The gamma-compensated ionization chamber was 21891 1 29 calibrated by single irradiations of bare 21891 1 30 and cadmium-covered gold plates. 21891 1 31 DETECTOR (NAICR) 3 Inch * 3 inch NaI scintillator, 21891 1 32 HARSHAW 12S12/GR, phototube RCA8054. 21891 1 33 ANALYSIS Cross sections were determined from measured activitied21891 1 34 number of target atoms and 'ft' (called 'flux-time 21891 1 35 factor', containing all information of neutron fluxes 21891 1 36 and timing of intermittent irradiation). 21891 1 37 MONITOR The gamma-compensated ionization chamber was 21891 1 38 calibrated by single irradiations of bare 21891 1 39 and cadmium-covered gold plates. 21891 1 40 CORRECTION For - 21891 1 41 self-absorption 21891 1 42 self-shielding 21891 1 43 ERR-ANALYS (ERR-T) Total uncertainty including 21891 1 44 - statistical uncertainty 21891 1 45 (ERR-1) uncertainty of detector efficiency 21891 1 46 - other systematic uncertainties 21891 1 47 HISTORY (19831117C) A.L. 21891 1 48 (20230208A) SD:Updated to new date formats,lower case. 21891 1 49 Corrections in all Subents. 21891 1 50 ENDBIB 48 0 21891 1 51 COMMON 2 3 21891 1 52 EN-DUMMY ERR-1 21891 1 53 EV PER-CENT 21891 1 54 0.0253 5. 21891 1 55 ENDCOMMON 3 0 21891 1 56 ENDSUBENT 55 0 21891 199999 SUBENT 21891002 20230208 231321891 2 1 BIB 5 6 21891 2 2 REACTION (79-AU-197(N,G)79-AU-198,,SIG,,MXW) 21891 2 3 DECAY-DATA (79-AU-198-G,2.7D,DG,412.,0.997) 21891 2 4 FLAG (1.) Experiment 1. 21891 2 5 (2.) experiment 2. 21891 2 6 STATUS (TABLE) Table 2 from Nucl.Instr.Meth.,151(1978)567 21891 2 7 HISTORY (20230208U) SD: BIB updated. 21891 2 8 ENDBIB 6 0 21891 2 9 NOCOMMON 0 0 21891 2 10 DATA 3 2 21891 2 11 DATA ERR-T FLAG 21891 2 12 B B NO-DIM 21891 2 13 93.7 6.7 1. 21891 2 14 98.9 7.3 2. 21891 2 15 ENDDATA 4 0 21891 2 16 ENDSUBENT 15 0 21891 299999 SUBENT 21891003 20230208 231321891 3 1 BIB 5 7 21891 3 2 REACTION (49-IN-115(N,G)49-IN-116-M1+M2,,SIG,,MXW) 21891 3 3 DECAY-DATA (49-IN-116-M1,54.MIN,DG,1293.,0.85) 21891 3 4 FLAG (3.) Experiment 3. 21891 3 5 (4.) experiment 4. 21891 3 6 STATUS (TABLE) Table 2 from Nucl.Instr.Meth.,151(1978)567 21891 3 7 HISTORY (20230208A) SD: SF4: In-116-M -> In-116M1+M2 in 21891 3 8 REACTION code. 21891 3 9 ENDBIB 7 0 21891 3 10 NOCOMMON 0 0 21891 3 11 DATA 3 2 21891 3 12 DATA ERR-T FLAG 21891 3 13 B B NO-DIM 21891 3 14 153.9 11.8 3. 21891 3 15 157.3 11.5 4. 21891 3 16 ENDDATA 4 0 21891 3 17 ENDSUBENT 16 0 21891 399999 ENDENTRY 3 0 2189199999999