ENTRY 22861 20180125 226522861 0 1 SUBENT 22861001 20180125 226522861 1 1 BIB 12 46 22861 1 2 TITLE Measurement of thermal neutron cross-sections and 22861 1 3 resonance integrals for Ga-71(n,gamma)Ga-72 and 22861 1 4 As-75(n,gamma)As-76 by using Am-241-Be isotopic 22861 1 5 neutron source 22861 1 6 AUTHOR (M.Karadag,H.Yucel,M.Tan,A.Ozmen) 22861 1 7 INSTITUTE (2TUKANR) 22861 1 8 (2TUKTUK) Cazi University, Turkey. 22861 1 9 REFERENCE (J,NIM/A,501,524,2003) 22861 1 10 SAMPLE The irradiations of the samples were carried out within22861 1 11 and without a cylindrical cadmium shield case. The 22861 1 12 irradiations for eight samples for each element, which 22861 1 13 are individually prepared from the fresh stocks, were 22861 1 14 repeated four time, that is, a set of four, with and 22861 1 15 without Cd-irradiation data for MnO(2), Ga(2)O(3), 22861 1 16 As(2)O(3) are obtained. The samples were diluted to 22861 1 17 minimize self-shielding during irradiation. For this, 22861 1 18 the samples were mechanically mixed with finely grained22861 1 19 Al(2)O(3) powder by 98.6-96%, since Al-27 isotope has 22861 1 20 low neutron absorption cross section. 22861 1 21 The irradiation times for the (n,gamma) reactions of 22861 1 22 Mn-55, Ga-71, As-75 were chosen for a period of 22861 1 23 3-6 half-lives, yielding enough activity to be measured22861 1 24 in gamma-ray counting system. 22861 1 25 ADD-RES (COMP) The results are discussed and compared with 22861 1 26 previous measurements and the evaluated data in 22861 1 27 ENDF/B-VI and JENDL-3.2. 22861 1 28 Using the nuclear data and the measured cadmium ratios 22861 1 29 for W- and Au-, alpha-epithermal neutron spectrum shape22861 1 30 factor has been found to be 0.116+-0.006 for the sample22861 1 31 irradiation position. 22861 1 32 DETECTOR A reverse-electrode germanium detector with a total 22861 1 33 active volume of 100-cm*3. 22861 1 34 INC-SPECT *EN-RSL* the energy resolution N-type Ge-detector with 22861 1 35 be-window was 1.80-keV for 1332.5-keV of Co-60 and 22861 1 36 0.97-keV for 122-keV of Co-57 and its relative 22861 1 37 efficiency was 22.6%. 22861 1 38 INC-SOURCE (AM-BE) The three 592-GBq Am-241-Be isotopic neutron 22861 1 39 sources immersed in paraffin moderator shielded with 22861 1 40 lead. 22861 1 41 METHOD (ACTIV) 22861 1 42 STATUS (TABLE) Tables 6,7 of NIM/A,501,524 22861 1 43 HISTORY (20041127C) 22861 1 44 (20041222U) Last checking has been done. 22861 1 45 (20170824A) SD: FACILITY deleted. INC-SOURCE update. 22861 1 46 ERR-ANALYS re-compiled. BIB update in all Subents. 22861 1 47 (20180125A) On. Major revision in 004. 22861 1 48 ENDBIB 46 0 22861 1 49 NOCOMMON 0 0 22861 1 50 ENDSUBENT 49 0 22861 199999 SUBENT 22861002 20170824 226522861 2 1 BIB 7 27 22861 2 2 REACTION (31-GA-71(N,G)31-GA-72,,SIG) 22861 2 3 MONITOR (25-MN-55(N,G)25-MN-56,,SIG) 22861 2 4 DECAY-DATA (31-GA-72,14.10HR,DG,834.03,0.9563,DG,629.96,0.248) 22861 2 5 REL-REF (A,,G.Gleason,J,RRL,23,317,1975) 22861 2 6 (A,,T.B.Ryves,J,NE,25,129,1971) 22861 2 7 (D,,L.Koester+,J,ZP/A,318,347,1984) 22861 2 8 (D,,W.S.Lyon,J,NSE,8,378,1960) 22861 2 9 CORRECTION The thermal neutron self-shielding factor is 0.998. 22861 2 10 ERR-ANALYS (ERR-T) Total uncertainty includes: 22861 2 11 (ERR-S) Statistical error (statistics of +-1.65sigma). 22861 2 12 (ERR-1) Error in detector efficiency 22861 2 13 (ERR-2) Error in mass sample 22861 2 14 (ERR-3) Error in half-life 22861 2 15 (ERR-4) Error in branching ratio 22861 2 16 (ERR-5) Error in self-shielding factor 22861 2 17 (ERR-6) Error in isotopic abundance 22861 2 18 (ERR-7) total uncertainty of Mn production includes: 22861 2 19 * statistical error - 0.39% 22861 2 20 * Error in detector efficiency is 2.75%. 22861 2 21 * Error in mass sample is 0.01%. 22861 2 22 * Error in half-life is 0.004%. 22861 2 23 * Error in branching ratio is 0.30%. 22861 2 24 * Error in self-shielding factor is 0.01%. 22861 2 25 * Error in monitor thermal neutr. cross-sect. is 0.75%22861 2 26 HISTORY (20170824A) SD: ERR-ANALYS re-compiled. BIB update. 22861 2 27 MONIT deleted. SF8=MXW deleted. (sigma0 is corrected 22861 2 28 for the Westcott factor). COMMENT -> CORRECTION. 22861 2 29 ENDBIB 27 0 22861 2 30 COMMON 6 3 22861 2 31 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 22861 2 32 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 22861 2 33 2.71 0.01 0.14 0.07 0.01 0.016 22861 2 34 ENDCOMMON 3 0 22861 2 35 DATA 5 1 22861 2 36 EN-MEAN DATA ERR-T ERR-S ERR-7 22861 2 37 EV B B PER-CENT PER-CENT 22861 2 38 0.0253 4.41 0.18 0.42 0.1 22861 2 39 ENDDATA 3 0 22861 2 40 ENDSUBENT 39 0 22861 299999 SUBENT 22861003 20180125 226522861 3 1 BIB 8 23 22861 3 2 REACTION (31-GA-71(N,G)31-GA-72,,RI) 22861 3 3 DECAY-DATA (31-GA-72,14.10HR,DG,834.03,0.9563,DG,629.96,0.248) 22861 3 4 MONITOR (25-MN-55(N,G)25-MN-56,,RI) 22861 3 5 DECAY-MON (25-MN-56,2.5789HR,DG,846.75,0.989) 22861 3 6 REL-REF (A,,A.Simonits+,J,JRN,81,397,1984) 22861 3 7 (D,,R.Van Der Linden+,J,JRC,11,133,1972) Less on 58% 22861 3 8 THAN present measurement. 22861 3 9 (D,,S.P.Harris+,J,PR,79,11,1950) 22861 3 10 CORRECTION The epithermal self-shielding factors is 0.907. 22861 3 11 ERR-ANALYS (ERR-T) Total uncertainty includes: 22861 3 12 (ERR-1) error in cadmium ratio is 1.67% 22861 3 13 (ERR-2) Error in self-shielding factor 0.15% 22861 3 14 (ERR-3) Error in reference thermal neutron cross-sect. 22861 3 15 (ERR-4) Error in alpha-shape parameter is 3.02%. 22861 3 16 (ERR-5) Error in normalization: 22861 3 17 * Error in cadmium ratio is 1.60%. 22861 3 18 * Error in self-shielding factor 0.20%. 22861 3 19 * Error in reference thermal neutron cross-sect. 0.75%22861 3 20 * Error in alpha-shape parameter is 3.61%. 22861 3 21 * Monitor resonance integral cross-section 2.14% 22861 3 22 HISTORY (20170824A) SD: ERR-ANALYS re-compiled. BIB update. 22861 3 23 MONIT deleted. 22861 3 24 (20180125U) On. COMMENT->CORRECTION. 22861 3 25 ENDBIB 23 0 22861 3 26 COMMON 4 3 22861 3 27 ERR-1 ERR-2 ERR-3 ERR-4 22861 3 28 PER-CENT PER-CENT PER-CENT PER-CENT 22861 3 29 1.67 0.15 4.12 3.02 22861 3 30 ENDCOMMON 3 0 22861 3 31 DATA 4 1 22861 3 32 EN-MIN DATA ERR-T ERR-5 22861 3 33 EV B B B 22861 3 34 0.55 32.3 2.3 0.3 22861 3 35 ENDDATA 3 0 22861 3 36 ENDSUBENT 35 0 22861 399999 SUBENT 22861004 20180125 226522861 4 1 BIB 8 27 22861 4 2 REACTION (33-AS-75(N,G)33-AS-76,,SIG) 22861 4 3 DECAY-DATA (33-AS-76,25.87HR,DG,559.10,0.45) 22861 4 4 REL-REF (D,,W.S.Lyon,J,NSE,8,378,1960) About 61% than the 22861 4 5 present measurement. 22861 4 6 MONITOR (25-MN-55(N,G)25-MN-56,,SIG) 22861 4 7 DECAY-MON (25-MN-56,2.5789HR,DG,846.75,0.989) 22861 4 8 CORRECTION The thermal neutron self-shielding factors is 0.997. 22861 4 9 ERR-ANALYS (ERR-T) Total uncertainty includes: 22861 4 10 (ERR-S) Statistical error (statistics of +-1.65sigma). 22861 4 11 (ERR-1) Error in detector efficiency 22861 4 12 (ERR-2) Error in mass sample 22861 4 13 (ERR-3) Error in half-life 22861 4 14 (ERR-4) Error in branching ratio 22861 4 15 (ERR-5) Error in self-shielding factor 22861 4 16 (ERR-6) Error in isotopic abundance 22861 4 17 (ERR-7) Normalization error: 22861 4 18 * statistical error - 0.39% 22861 4 19 * Error in detector efficiency is 2.75%. 22861 4 20 * Error in mass sample is 0.01%. 22861 4 21 * Error in half-life is 0.004%. 22861 4 22 * Error in branching ratio is 0.30%. 22861 4 23 * Error in self-shielding factor is 0.01%. 22861 4 24 * Error in monitor thermal neutr. cross-sect. is 0.75%22861 4 25 HISTORY (20170824A) SD: ERR-ANALYS re-compiled. BIB update. 22861 4 26 MONIT deleted. SF8=MXW deleted. (sigma0 is corrected 22861 4 27 for the Westcott factor). 22861 4 28 (20180125A) On. MONIT-ERR->ERR-7. COMMENT->CORRECTION. 22861 4 29 ENDBIB 27 0 22861 4 30 COMMON 6 3 22861 4 31 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 22861 4 32 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 22861 4 33 2.23 0.01 0.19 4.44 0.01 0.016 22861 4 34 ENDCOMMON 3 0 22861 4 35 DATA 5 1 22861 4 36 EN-MEAN DATA ERR-T ERR-S ERR-7 22861 4 37 EV B B PER-CENT B 22861 4 38 0.0253 4.15 0.24 0.26 0.1 22861 4 39 ENDDATA 3 0 22861 4 40 ENDSUBENT 39 0 22861 499999 SUBENT 22861005 20180125 226522861 5 1 BIB 8 22 22861 5 2 REACTION (33-AS-75(N,G)33-AS-76,,RI) 22861 5 3 DECAY-DATA (33-AS-76,25.87HR,DG,559.10,0.45) 22861 5 4 REL-REF (A,,S.I.Kafala,J,JRN,215,193,1997) 22861 5 5 (D,,R.Van Der Linden+,J,JRC,11,133,1972) Less on 35% 22861 5 6 than the present measurement. 22861 5 7 MONITOR (25-MN-55(N,G)25-MN-56,,RI) 22861 5 8 DECAY-MON (25-MN-56,2.5789HR,DG,846.75,0.989) 22861 5 9 CORRECTION The epithermal self-shielding factor is 0.900. 22861 5 10 ERR-ANALYS (ERR-T) Total uncertainty in As-75 includes: 22861 5 11 (ERR-1) error in cadmium ratio is 1.70% 22861 5 12 (ERR-2) Error in self-shielding factor 0.50% 22861 5 13 (ERR-3) Error in reference thermal neutron cross-sect. 22861 5 14 (ERR-4) Error in alpha-shape parameter is 2.77%. 22861 5 15 (ERR-5) Normalization error: 22861 5 16 * Error in cadmium ratio is 1.60%. 22861 5 17 * Error in self-shielding factor 0.20%. 22861 5 18 * Error in reference thermal neutron cross-sect. 0.75%22861 5 19 * Error in alpha-shape parameter is 3.61%. 22861 5 20 * Monitor resonance integral cross-section 2.14% 22861 5 21 HISTORY (20170824A) SD: ERR-ANALYS re-compiled. BIB update. 22861 5 22 MONIT deleted. COMMENT -> CORRECTION. 22861 5 23 (20180125U) On. PART-DET deleted. 22861 5 24 ENDBIB 22 0 22861 5 25 COMMON 4 3 22861 5 26 ERR-1 ERR-2 ERR-3 ERR-4 22861 5 27 PER-CENT PER-CENT PER-CENT PER-CENT 22861 5 28 1.70 0.50 2.22 2.77 22861 5 29 ENDCOMMON 3 0 22861 5 30 DATA 4 1 22861 5 31 EN-MIN DATA ERR-T ERR-5 22861 5 32 EV B B B 22861 5 33 0.55 63.5 3.8 0.3 22861 5 34 ENDDATA 3 0 22861 5 35 ENDSUBENT 34 0 22861 599999 ENDENTRY 5 0 2286199999999