ENTRY 22964 20230518 231722964 0 1 SUBENT 22964001 20230518 231722964 1 1 BIB 15 54 22964 1 2 TITLE Measurement of thermal neutron cross section and 22964 1 3 resonance integral for (n,gamma) reaction in 152Sm 22964 1 4 AUTHOR (M.Karadag, H.Yuecel, M.Guray Budak) 22964 1 5 INSTITUTE (2TUKANR) Experimental site 22964 1 6 (2TUKGZU) 22964 1 7 REFERENCE (J,ANE,34,188,2007) Main reference, data are given 22964 1 8 REL-REF (M,22871001,H.Yuecel+,J,ANE,32,1,2005) Experimental 22964 1 9 and analysis details 22964 1 10 (I,,H.Yuecel+,J,ANE,31,681,2004) Experimental details 22964 1 11 METHOD (ACTIV,SITA) 22964 1 12 DETECTOR (HPGE) Resolution 1.80 keV at 1332.5 keV g-energy of 22964 1 13 Co-60 and 0.97 keV for 122 keV of Co-57. Relative 22964 1 14 efficiency is 22.6%. Resolution of detector was 22964 1 15 determined using standard radionuclides of Cd-109, 22964 1 16 Co-57, Cr-51, Te-123m, Sn-113, Sr-85, Cs-137, 22964 1 17 Co-60 and Y-88 22964 1 18 INC-SOURCE (AM-BE) Three 592 GBq 241Am-Be isotopic neutron source 22964 1 19 immersed in paraffin moderator shielded with lead 22964 1 20 INC-SPECT Alpha-beryllium source was immersed in paraffin. 22964 1 21 Thermal neutron flux was (1.5+-0.2)E+4 and 22964 1 22 epithermal neutron flux was (1.4+-0.1)E+3 n/cm2/sec. 22964 1 23 Each irradiations were performed with and without 22964 1 24 cadmium shield 22964 1 25 DECAY-DATA (62-SM-153,46.50HR,DG,69.67,0.0485, 22964 1 26 DG,103.18,0.298, 22964 1 27 DG,760.) Last three gamma lines - from 22964 1 28 the excited Eu-153 obtained via B- decay of Sm-153 22964 1 29 SAMPLE Manganese Mn-O2 and Samarium Sm2-O3 oxide powders were22964 1 30 diluted with the finely grained Al2-O3 powder by 22964 1 31 99.0 - 96.6%. Each sample was filled in polystyrene 22964 1 32 cylindrical tube (height/diam = aprx 2, walls 1 mm 22964 1 33 thick, internal diameter 5.0 mm) and irradiated with 22964 1 34 and without cylindrical cadmium shield case 22964 1 35 COMMENT Values below are similar to those given in REF.2, 22964 1 36 SUBENT 22964001 22964 1 37 ERR-ANALYS (ERR-EDD) Error of energy value for Sm-153, 103 keV 22964 1 38 line 22964 1 39 CORRECTION Corrections for background were made with the help of 22964 1 40 irradiating a bare cadmium case, for self-shielding - 22964 1 41 with the help of procedure given in J,ANE,31,681,2004 22964 1 42 Following information is used for calculation thermal 22964 1 43 neutron self-shielding correction factor: 22964 1 44 Element Atomic weight, Microscopic cross-sections (b)22964 1 45 M (g/mol) --------------------------- 22964 1 46 Absorption, Scattering, Total 22964 1 47 8-O 15.9994 1.9/10**4 3.78 3.78 22964 1 48 13Al 26.9815 0.231 1.41 1.64 22964 1 49 25Mn 54.9380 13.41 2.17 15.58 22964 1 50 was corrected in Subents 2,3. ASSUMED, MISC-COL were 22964 1 51 deleted; information moved to CORRECTION. 22964 1 52 HISTORY (20070720C) SM 22964 1 53 (20130203A) SD: INC-SOURCE was corrected. ASSUMED, 22964 1 54 MISC-COL were deleted; information moved to CORRECTION.22964 1 55 (20230518A) SD: Corrections in Subents 002, 003. 22964 1 56 ENDBIB 54 0 22964 1 57 COMMON 1 3 22964 1 58 ERR-EDD 22964 1 59 KEV 22964 1 60 0.17 22964 1 61 ENDCOMMON 3 0 22964 1 62 ENDSUBENT 61 0 22964 199999 SUBENT 22964002 20230518 231722964 2 1 BIB 9 44 22964 2 2 REACTION (62-SM-152(N,G)62-SM-153,,SIG) 22964 2 3 MONITOR (25-MN-55(N,G)25-MN-56,,SIG) 22964 2 4 MONIT-REF (,V.McLane+,R,BNL-NCS-44945,2001) Nuclear datafile 22964 2 5 ENDF/B-VI 22964 2 6 DECAY-MON (25-MN-56,2.5789HR,DG,846.754,0.989) 22964 2 7 REL-REF (A,,V.P.Kolotov+,J,JRN,257,501,2003) 22964 2 8 (A,,F.De Corte+,J,JRN,257,493,2003) 22964 2 9 (A,,R.L.Zimmerman+,J,NP/A,95,683,1967) 22964 2 10 (A,,A.Simonits+,J,JRN,81,397,1984) 22964 2 11 (A,,V.McLane+,R,BNL-NCS-44945,2001), ALSO 22964 2 12 JEFF-3.1 (2005), IAEA (1987), JENDL-3.3(2002), 22964 2 13 BROND 2.0(1998) 22964 2 14 (D,,S.I.Kafala+,J,JRN,215,193,1997) 22964 2 15 (D,,F.De Corte+,J,JRN,133,43,1989) 22964 2 16 (D,,E.Fehr+,R,KAPL-2000-12,(1),3,1960) 22964 2 17 MISC-COL (MISC6) Thermal neutron self-shielding 22964 2 18 ERR-ANALYS (ERR-T) Total error of Sm-152(n,g) as the square root 22964 2 19 of the quadratic sum of all its constituents 22964 2 20 (ERR-S) Statistical error for 1.65*(dispersion) 22964 2 21 confidence level for Sm-152 22964 2 22 (ERR-1) Error of detection efficiency for Sm-152 22964 2 23 (ERR-2) Error of the sample mass for Sm-152 22964 2 24 (ERR-3) Error of the HALF-LIFE (not specified) 22964 2 25 (ERR-4) Error of the isotopic abundance 22964 2 26 (ERR-5) Error of the Sm-153 gamma-ray emission 22964 2 27 probability 22964 2 28 (ERR-6) Error of the Sm-152 thermal neutron self- 22964 2 29 shielding factor 22964 2 30 (ERR-7) Error of the Sm-152 cadmium transmission 22964 2 31 factor 22964 2 32 (ERR-8) Statistical error for 1.65*(dispersion) 22964 2 33 confidence level for 55-Mn 22964 2 34 (ERR-9) Error of detection efficiency for 55-Mn 22964 2 35 (ERR-10) Error of the sample mass for 55-Mn 22964 2 36 (ERR-11) Error of the 56-Mn half-life 22964 2 37 (ERR-12) Error of the Mn-56 gamma-ray emission 22964 2 38 probability 22964 2 39 (ERR-13) Error of the 55Mn thermal neutron self- 22964 2 40 shielding factor 22964 2 41 (MONIT-ERR) Monitor thermal neuron cross section error 22964 2 42 STATUS (TABLE) From table 4 of Ann.Nucl.En.,34,188,2007 22964 2 43 HISTORY (20230518A) SD: ERR-T and MONIT-ERR deleted from COMMON22964 2 44 section. MONIT-ERR deleted from DATA section. 22964 2 45 ERR-14 renamed: MONIT-ERR. 22964 2 46 ENDBIB 44 0 22964 2 47 COMMON 16 9 22964 2 48 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 22964 2 49 ERR-6 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 22964 2 50 ERR-12 ERR-13 MONIT-ERR MISC6 22964 2 51 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 22964 2 52 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 22964 2 53 PER-CENT PER-CENT PER-CENT NO-DIM 22964 2 54 0.18 2.55 0.01 0.45 0.60 1.3422964 2 55 0.1 0.80 0.39 2.75 0.01 0.00422964 2 56 0.30 0.1 0.75 0.913 22964 2 57 ENDCOMMON 9 0 22964 2 58 DATA 4 1 22964 2 59 EN DATA ERR-T MONIT 22964 2 60 EV B B B 22964 2 61 0.025 204.8 7.9 13.3 22964 2 62 ENDDATA 3 0 22964 2 63 ENDSUBENT 62 0 22964 299999 SUBENT 22964003 20230518 231722964 3 1 BIB 9 44 22964 3 2 REACTION (62-SM-152(N,G)62-SM-153,,RI) 22964 3 3 MONITOR (25-MN-55(N,G)25-MN-56,,RI) 22964 3 4 DECAY-MON (25-MN-56,2.5789HR,DG,846.754,0.989) 22964 3 5 MONIT-REF (,V.McLane+,R,BNL-NCS-44945,2001) Nuclear datafile 22964 3 6 ENDF/B-VI 22964 3 7 REL-REF (A,,V.P.Kolotov+,J,JRN,257,501,2003) 22964 3 8 (A,,S.I.Kafala+,J,JRN,215,193,1997) 22964 3 9 (A,,A.Simonits+,J,JRN,81,397,1984) 22964 3 10 (A,,F.De Corte+,J,JRN,133,43,1989) 22964 3 11 (A,,R.E.Heft,C,78MAYAG,,495,1978) , 22964 3 12 (A,,V.McLane+,R,BNL-NCS-44945,2001), also 22964 3 13 JEFF-3.1 (2005), IAEA (1987), JENDL-3.3(2002), 22964 3 14 BROND 2.0(1998) 22964 3 15 (D,,R.L.Macklin+,C,55GENEVA,5,96,1955) 22964 3 16 MISC-COL (MISC6) Epithermal neutron self-shielding 22964 3 17 (MISC7) Epithermal neutron spectrum shape parameter 22964 3 18 "A" IN THE EXPRESSION 1/E**(1+A) 22964 3 19 ERR-ANALYS (ERR-T) Total error as the square root of the 22964 3 20 quadratic sum for Sm-152 of all its constituents 22964 3 21 Value (214 b) presented in the table is slightly 22964 3 22 different (7.04%). 22964 3 23 (ERR-1) Error of the epithermal neutron spectrum 22964 3 24 shape parameter "a" 22964 3 25 (ERR-2) Error of the cadmium cut-off energy 22964 3 26 (ERR-3) Error of the cadmium ration for MN-55 22964 3 27 (ERR-4) Error of cadmium ratio for Sm-152 22964 3 28 (ERR-5) Error of the thermal neutron self-shielding 22964 3 29 factor for MN-55 sample 22964 3 30 (ERR-6) Error of the thermal neutron self-shielding 22964 3 31 factor for Sm152 sample 22964 3 32 (ERR-7) Error of the epithermal neutron self-shielding22964 3 33 factor for Mn-55 sample 22964 3 34 (ERR-8) Error of the epithermal neutron self-shielding22964 3 35 factor for Sm-152 sample 22964 3 36 (ERR-9) Error of the reference thermal neutron cross 22964 3 37 section for Mn-55 22964 3 38 (ERR-10) Error of the Mn-55 reference thermal neutrons 22964 3 39 cross section 22964 3 40 (ERR-11) Error of the Mn-55 effective resonance energy 22964 3 41 (ERR-12) Error of the Sm-152 effective resonance energy22964 3 42 (MONIT-ERR) Total error of the ref. resonance integral 22964 3 43 STATUS (TABLE) From table 4 of Ann.Nucl.En.,34,188,2007 22964 3 44 HISTORY (20230518A) SD: ERR-T and MONIT-ERR deleted from DATA 22964 3 45 section. 22964 3 46 ENDBIB 44 0 22964 3 47 COMMON 17 9 22964 3 48 ERR-T ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 22964 3 49 ERR-6 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 22964 3 50 ERR-12 MISC6 MISC7 MISC7-ERR MONIT-ERR 22964 3 51 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 22964 3 52 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 22964 3 53 PER-CENT NO-DIM NO-DIM NO-DIM PER-CENT 22964 3 54 7.42 2.41 0.58 1.71 3.24 0.10 22964 3 55 0.10 0.20 2.50 1.10 4.23 0.45 22964 3 56 0.09 0.903 0.083 0.016 3.13 22964 3 57 ENDCOMMON 9 0 22964 3 58 DATA 3 1 22964 3 59 EN-MIN DATA MONIT 22964 3 60 EV B B 22964 3 61 0.55 3038. 14. 22964 3 62 ENDDATA 3 0 22964 3 63 ENDSUBENT 62 0 22964 399999 ENDENTRY 3 0 2296499999999