ENTRY 23202 20151013 22452320200000001 SUBENT 23202001 20151013 22452320200100001 BIB 9 36 2320200100002 TITLE .Measurement of thermal neutron cross-section and 2320200100003 resonance integral for the 158Gd(n,gamma)159Gd 2320200100004 reaction by using a 55Mn monitor. 2320200100005 AUTHOR (M.Karadag, M.Gueray Budak, H.Yuecel) 2320200100006 INSTITUTE (2TUKGZU) M.Karadag, M.Gueray Budak 2320200100007 (2TUKANK) H.Yuecel 2320200100008 REFERENCE (J,ANE,63,199,2014) Data for Gd-158. 2320200100009 (J,ANE,62,274,2013) Data for Nd. 2320200100010 (J,ANE,62,178,2013) Data for Cs. 2320200100011 INC-SOURCE (AM-BE) Three Am241-Be sources immersed in paraffin 2320200100012 moderator shielded with lead bricks. 2320200100013 INC-SPECT At the sample irradiation position, thermal and 2320200100014 epithermal neutron fluxes were measured to be 2320200100015 (1.5 +- 0.2)*10**4 and (1.4 +- 0.1)*10**3 n/cm**2/s 2320200100016 respectively. The epithermal neutron spectrum shape 2320200100017 factor was experimentally determined as 0.083 +- 0.016 2320200100018 at the sample irradiation position. 2320200100019 METHOD (ACTIV) Activation. 2320200100020 -Irradiation times about 55-90 h for 158Gd, about 7-13h2320200100021 for 55Mn, after the irradiations the suitable waiting 2320200100022 times varying up to 20 min, counting periods between 2 2320200100023 and 24 hr. 2320200100024 - The irradiation times for the 55Mn and 148Nd were 2320200100025 chosen for a period of three to five half lives; 2320200100026 the counting times varied between 2 and 7 h for 149Nd 2320200100027 and between 2.5 and 10 h for 56Mn. 2320200100028 - the irradiation times for Cs and Mn were chosen for 2320200100029 a period of four to five half-lives. 2320200100030 (CADMB) Cadmium ratio method 2320200100031 CORRECTION Dead times were typically less than about 0.1%. 2320200100032 Background measurements were subtracted from the sample2320200100033 spectra. 2320200100034 Correction factors for gamma ray attenuation and for 2320200100035 true coincidence summing were used. 2320200100036 HISTORY (20131114C) M.M. 2320200100037 (20151013U) SD: Illegal "(" was removed from INC-SPECT.2320200100038 ENDBIB 36 0 2320200100039 NOCOMMON 0 0 2320200100040 ENDSUBENT 39 0 2320200199999 SUBENT 23202002 20131114 22372320200200001 BIB 9 65 2320200200002 REACTION (64-GD-158(N,G)64-GD-159,,SIG) 2320200200003 SAMPLE Gd(2)O(3) powder, purity > 99.99%, from Aldrich corp. 2320200200004 Mixed with Al(2)O(3) powder to minimize errors due to 2320200200005 self-shielding effect. Diluted sample (3.2% Gd(2)O(3)+ 2320200200006 96.8% Al(2)O(3)) and (3.4% MnO(2) + 96.6% Al(2)O(3)) 2320200200007 were filled in small polystyrene tubes with 2320200200008 height/diameter about 2 and wall thickness of 1 mm. 2320200200009 Ten diluted Gd samples (each mass of about 0.8 g) were 2320200200010 individually prepared. Five were used for Cd-covered 2320200200011 irradiation and the other were used for obtaining bare 2320200200012 irradiation data. The same preparation - for ten Mn 2320200200013 samples. 2320200200014 (64-GD-158,NAT=0.2484) Isotopic abundance 24.84+-0.07 %2320200200015 (25-MN-55,NAT=1.00) 2320200200016 DECAY-DATA (64-GD-159,18.479HR,DG,363.5430,0.1178) 2320200200017 18.479+-0.004 hr, 363.5430+-0.0018 keV, 11.78+-0.60%. 2320200200018 MONITOR (25-MN-55(N,G)25-MN-56,,SIG) 13.3+-0.1 b. 2320200200019 DECAY-MON (25-MN-56,2.5789HR,DG,846.754,0.989) 2320200200020 2.5789+-0.0001 hr, 846.754+-0.020 keV, 98.9+-0.3 % . 2320200200021 DETECTOR (HPGE) Coaxial p-type HPGe detector (Canberra GC11021) 2320200200022 to measure induced activity. Relative efficiency of 2320200200023 120.8%, energy resolution of 1.95 keV, peak-to-Compton 2320200200024 ratio of 85.7:1 at 1332.5 keV of 60Co. 2320200200025 The samples were counted at a distance of 10 cm from 2320200200026 the detector. 2320200200027 Gamma detection efficiency was determined using a 2320200200028 multi-nuclide standard in sand matrix (density: 1.7 2320200200029 g/cm3) spiked with 241Am, 109Cd, 57Co, 123mTe, 51Cr, 2320200200030 113Sn, 85Sr, 137Cs, 60Co, 88Y radionuclides. 2320200200031 ANALYSIS Westcott correction factors g(20 degC) 1.0009 for 158Gd2320200200032 and 1.0003 for 55Mn isotopes were used in analysis. 2320200200033 Calculated neutron self-shielding factors for diluted 2320200200034 MnO2 and Gd2O3 samples: 2320200200035 Mn - 0.997 for thermal neutrons, 2320200200036 Gd - 0.921 for thermal neutrons. 2320200200037 Correction factor for gamma ray attenuation 2320200200038 for Mn - 1.012, for Gd - 1.020. 2320200200039 True coincidence summing factor 2320200200040 for Mn - 0.992, for Gd - 1.000 . 2320200200041 ERR-ANALYS Uncertainties due to: 2320200200042 (ERR-1) Peak area for Gd 0.85% , based on counting 2320200200043 statistics of +-1.65sigma. 2320200200044 (ERR-2) Detection efficiency for Gd 2.55% 2320200200045 (ERR-3) Mass of Gd sample 0.01% 2320200200046 (ERR-4) Isotopic abundance for Gd 0.28% 2320200200047 (ERR-5) Half-life for Gd 0.02% 2320200200048 (ERR-6) Gamma-ray emission probability for Gd 5.1% 2320200200049 (ERR-7) Thermal neutron self-shielding factor for Gd 2320200200050 0.5% 2320200200051 (ERR-8) g(20 degC) - Westcott factor for Gd 0.1% 2320200200052 (ERR-9) Peak area for Mn 0.40% , based on counting 2320200200053 statistics of +-1.65sigma. 2320200200054 (ERR-10) Detection efficiency for Mn 2.75% 2320200200055 (ERR-11) Mass of Mn sample 0.01% 2320200200056 (ERR-12) Half-life for Mn 0.004% 2320200200057 (ERR-13) Gamma-ray emission probability for Mn 0.30% 2320200200058 (ERR-14) Thermal neutron self-shielding factor for Mn 2320200200059 0.1% 2320200200060 (ERR-15) g(20 degC) - Westcott factor for Mn 0.1% 2320200200061 (MONIT-ERR) Monitor thermal neutron cross section 2320200200062 0.75% 2320200200063 Total uncertainty for Mn 2.90% 2320200200064 (ERR-T) Total uncertainty 5.79% =0.14 b. 2320200200065 STATUS (TABLE) Table 3 of J,ANE,63,199,2014 . 2320200200066 Uncertainties - Table 4. 2320200200067 ENDBIB 65 0 2320200200068 COMMON 15 9 2320200200069 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2320200200070 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 ERR-12 2320200200071 ERR-13 ERR-14 ERR-15 2320200200072 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2320200200073 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2320200200074 PER-CENT PER-CENT PER-CENT 2320200200075 0.85 2.55 0.01 0.28 0.02 5.1 2320200200076 0.5 0.1 0.40 2.75 0.01 0.004 2320200200077 0.30 0.1 0.1 2320200200078 ENDCOMMON 9 0 2320200200079 DATA 6 1 2320200200080 EN DATA ERR-T ERR-T MONIT MONIT-ERR 2320200200081 EV B B PER-CENT B PER-CENT 2320200200082 0.0253 2.15 0.14 5.79 13.3 0.75 2320200200083 ENDDATA 3 0 2320200200084 ENDSUBENT 83 0 2320200299999 SUBENT 23202003 20131114 22372320200300001 BIB 9 91 2320200300002 REACTION (64-GD-158(N,G)64-GD-159,,RI) 2320200300003 DECAY-DATA (64-GD-159,18.479HR,DG,363.5430,0.1178) 2320200300004 18.479+-0.004 hr, 363.5430+-0.0018 keV, 11.78+-0.60%. 2320200300005 SAMPLE Gd(2)O(3) powder, purity > 99.99%, from Aldrich corp. 2320200300006 Mixed with Al(2)O(3) powder to minimize errors due to 2320200300007 self-shielding effect. Diluted sample (3.2% Gd(2)O(3)+ 2320200300008 96.8% Al(2)O(3)) and (3.4% MnO(2) + 96.6% Al(2)O(3)) 2320200300009 were filled in small polystyrene tubes with 2320200300010 height/diameter about 2 and wall thickness of 1 mm. 2320200300011 Ten diluted Gd samples (each mass of about 0.8 g) were 2320200300012 individually prepared. Five were used for Cd-covered 2320200300013 irradiation and the other were used for obtaining bare 2320200300014 irradiation data. The same preparation - for ten Mn 2320200300015 samples. 2320200300016 (64-GD-158,NAT=0.2484) Isotopic abundance 24.84+-0.07 %2320200300017 (25-MN-55,NAT=1.00) 2320200300018 MONITOR ((MONIT1)25-MN-55(N,G)25-MN-56,,RI) Main monitor. 2320200300019 14.0+-0.3 2320200300020 ((MONIT2)25-MN-55(N,G)25-MN-56,,SIG) Thermal c-s. 2320200300021 13.3+-0.1 b. 2320200300022 DETECTOR (HPGE) Coaxial p-type HPGe detector (Canberra GC11021) 2320200300023 to measure induced activity. Relative efficiency of 2320200300024 120.8%, energy resolution of 1.95 keV, peak-to-Compton 2320200300025 ratio of 85.7:1 at 1332.5 keV of 60Co. 2320200300026 The samples were counted at a distance of 10 cm from 2320200300027 the detector. 2320200300028 Gamma detection efficiency was determined using a 2320200300029 multi-nuclide standard in sand matrix (density: 1.7 2320200300030 g/cm3) spiked with 241Am, 109Cd, 57Co, 123mTe, 51Cr, 2320200300031 113Sn, 85Sr, 137Cs, 60Co, 88Y radionuclides. 2320200300032 ANALYSIS Westcott correction factors g(20 degC) 1.0009 for 158Gd2320200300033 and 1.0003 for 55Mn isotopes were used in analysis. 2320200300034 Thermal neutron self-shielding factor for Mn 0.997, 2320200300035 thermal neutron self-shielding factor for GD 0.921, 2320200300036 epithermal neutron self-shielding factor for Mn 0.903, 2320200300037 epithermal neutron self-shielding factor for Gd 0.944 2320200300038 were estimated by the simplified procedure, taking into2320200300039 account the necessary nuclear data(resonance parameter,2320200300040 absorption, scattering and total microscopic cross 2320200300041 sections) taken from JENDL-4.0 (Shibata+,2011) and 2320200300042 ENDF/B-VII.1 (Chadwick+,2011) on-line data libraries. 2320200300043 Effective resonance energy for Mn - 468+-51 eV, 2320200300044 for Gd - 49.6 +- 10.4 eV . 2320200300045 REL-REF (R,,K.Shibata+,J,NSE,48,1,2011) 2320200300046 (R,,M.B.Chadwick+,J,NDS,112,2887,2011) 2320200300047 ERR-ANALYS Uncertainties due to: 2320200300048 (ERR-1) Alpha - shape parameter 1.74%. 2320200300049 (ERR-2) Cadmium cut-off energy 0.60%. 2320200300050 (ERR-3) Cadmium ratio of 56Mn 0.65%. 2320200300051 (ERR-4) Cadmium ratio of 159Gd 5.46%. 2320200300052 (ERR-5) Thermal neutron self-shielding factor for Mn 2320200300053 sample 0.10%. 2320200300054 (ERR-6) Thermal neutron self-shielding factor for Gd 2320200300055 sample 0.50%. 2320200300056 (ERR-7) Epithermal neutron self-shielding factor for Mn2320200300057 sample 0.20%. 2320200300058 (ERR-8) Epithermal neutron self-shielding factor for Gd2320200300059 sample 2.00%. 2320200300060 (ERR-9) Reference resonance integral cross-section of 2320200300061 55Mn 1.80%. 2320200300062 (ERR-10) Reference thermal neutron cross section of 2320200300063 55Mn 0.63%. 2320200300064 (ERR-11) Reference thermal neutron cross section of 2320200300065 158Gd 6.48%. 2320200300066 (ERR-12) g (20 degC) - Westcott factor of 55Mn 0.08%. 2320200300067 (ERR-13) g (20 degC) - Westcott factor of 158Gd 0.10%. 2320200300068 (ERR-14) Effective resonance energy of 55Mn 0.44%. 2320200300069 (ERR-15) Effective resonance energy of 158Gd 1.68%. 2320200300070 (ERR-T) Total uncertainty, 9.31%. 2320200300071 Relative uncertainties on the resonance integral value 2320200300072 were defined by relative uncertainty multiplied by 2320200300073 propagation factor : 2320200300074 Relative uncertainty,% Propagation factor 2320200300075 ERR-1 19.3 0.09 2320200300076 ERR-2 15. 0.04 2320200300077 ERR-3 0.61 1.07 2320200300078 ERR-4 1.60 3.41 2320200300079 ERR-5 0.1 1.00 2320200300080 ERR-6 0.5 1.00 2320200300081 ERR-7 0.2 1.00 2320200300082 ERR-8 2. 1.00 2320200300083 ERR-9 2.14 0.84 2320200300084 ERR-10 0.75 0.84 2320200300085 ERR-11 6.48 1.00 2320200300086 ERR-12 0.1 0.84 2320200300087 ERR-13 0.1 1.00 2320200300088 ERR-14 10.9 0.04 2320200300089 ERR-15 21.0 0.08 2320200300090 STATUS (TABLE) Table 3 of J,ANE,63,199,2014 . 2320200300091 Uncertainties - Table 5. 2320200300092 (DEP,23202002) Gd-158 n,g thermal c-s used to drive RI.2320200300093 ENDBIB 91 0 2320200300094 COMMON 15 9 2320200300095 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2320200300096 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 ERR-12 2320200300097 ERR-13 ERR-14 ERR-15 2320200300098 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2320200300099 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2320200300100 PER-CENT PER-CENT PER-CENT 2320200300101 1.74 0.60 0.65 5.46 0.10 0.50 2320200300102 0.20 2.00 1.80 0.63 6.48 0.08 2320200300103 0.10 0.44 1.68 2320200300104 ENDCOMMON 9 0 2320200300105 DATA 6 1 2320200300106 EN-MIN DATA ERR-T ERR-T MONIT1 MONIT2 2320200300107 EV B B PER-CENT B B 2320200300108 0.55 75.3 7.0 9.31 14.0 13.3 2320200300109 ENDDATA 3 0 2320200300110 ENDSUBENT 109 0 2320200399999 SUBENT 23202004 20131114 22372320200400001 BIB 9 68 2320200400002 REACTION (60-ND-148(N,G)60-ND-149,,SIG) 2320200400003 SAMPLE Nd(2)O(3) powder, purity > 99.99%, from Aldrich corp. 2320200400004 Mixed with Al(2)O(3) powder as (91.5% Al(2)O(3) + 2320200400005 8.5% Nd(2)O(3)) and (96.6% Al(2)O(3) + 3.4% MnO(2)) to 2320200400006 minimize errors due to self-shielding effect. 2320200400007 Each of the samples of MnO(2) and Nd(2)O(3) was 2320200400008 thoroughly mixed in an agate independently with using 2320200400009 Al(2)O(3) fine powder.Then ten diluted Nd-samples 2320200400010 having each mass of about 0.8 g were individually 2320200400011 filled in polystyrene tubes with height/diameter about 2320200400012 2 and 1 mm wall thickness. Five of them were used for 2320200400013 Cd-covered irradiation and other five - for obtaining 2320200400014 bare irradiation data. The same sample preparation 2320200400015 procedure was employed for ten Mn samples. 2320200400016 (60-ND-148,NAT=0.05756) Isotopic abundance 2320200400017 5.756+-0.021% . 2320200400018 (25-MN-55,NAT=1.00) 2320200400019 DECAY-DATA (60-ND-149,1.728HR,DG,211.309,0.259) 2320200400020 1.728+-0.001 hr, 211.309+-0.007 keV, 25.9+-1.0 % . 2320200400021 MONITOR (25-MN-55(N,G)25-MN-56,,SIG) 13.3+-0.1 b. 2320200400022 DECAY-MON (25-MN-56,2.5789HR,DG,846.754,0.989) 2320200400023 2.5789+-0.0001 hr, 846.754+-0.020 keV, 98.9+-0.3 % . 2320200400024 DETECTOR (HPGE) Coaxial n-type HPGe detector (Canberra GR2020) 2320200400025 to measure induced activity. Active volume about 2320200400026 100 cm**3. Measured relative efficiency of 22.6% at 2320200400027 1332.5 keV of 60Co, energy resolution 1.80 keV, 2320200400028 peak-to-Compton ratio of 53.5:1 at 1332.5 keV of 60Co. 2320200400029 Shielded by a 10 cm thick lead lined with 1 mm copper 2320200400030 sheets on all sides. 2320200400031 The gamma detection efficiency as a function of energy 2320200400032 was determined using the powder radioactive standard 2320200400033 containing a mixture of 241Am, 109Cd, 57Co, 123mTe, 2320200400034 51Cr, 113Sn, 85Sr, 137Cs, 60Co, 88Y radionuclides. 2320200400035 The samples were counted on the end-cap of detector. 2320200400036 ANALYSIS Westcott correction factors g(20 degC) 1.0004 for 148Nd2320200400037 and 1.0003 for 55Mn isotopes were not used in 2320200400038 calculations. 2320200400039 Calculated neutron self-shielding factors for diluted 2320200400040 MnO(2)and Nd(2)O(3) samples: 2320200400041 Mn - 0.997 for thermal neutrons, 2320200400042 Nd - 0.991 for thermal neutrons. 2320200400043 Correction factor for gamma ray attenuation 2320200400044 for Mn - 1.010, for Nd - 1.038. 2320200400045 True coincidence summing factor 2320200400046 for Mn - 0.963, for Nd - 1.000 . 2320200400047 ERR-ANALYS Uncertainties due to: 2320200400048 (ERR-1) Peak area for Nd 0.96% , based on counting 2320200400049 statistics of +-1.65sigma. 2320200400050 (ERR-2) Detection efficiency for Nd 2.51% 2320200400051 (ERR-3) Mass of Nd sample 0.01% 2320200400052 (ERR-4) Half-life for Nd 0.06% 2320200400053 (ERR-5) Isotopic abundance for Nd 0.36% 2320200400054 (ERR-6) Gamma-ray emission probability for Nd 3.86% 2320200400055 (ERR-7) Thermal neutron self-shielding factor for Nd 2320200400056 0.4% 2320200400057 (ERR-8) Peak area for Mn 0.39% , based on counting 2320200400058 statistics of +-1.65sigma. 2320200400059 (ERR-9) Detection efficiency for Mn 1.92% 2320200400060 (ERR-10) Mass of Mn sample 0.01% 2320200400061 (ERR-11) Half-life for Mn 0.004% 2320200400062 (ERR-12) Gamma-ray emission probability for Mn 0.30% 2320200400063 (ERR-13) Thermal neutron self-shielding factor for Mn 2320200400064 0.1% 2320200400065 (MONIT-ERR) Monitor thermal neutron cross section 0.75%2320200400066 Total uncertainty for Mn 2.12% . 2320200400067 (ERR-T) Total uncertainty 4.73% =0.14 b. 2320200400068 STATUS (TABLE) Table 3 of J,ANE,62,274,2013 . 2320200400069 Uncertainties - Table 4. 2320200400070 ENDBIB 68 0 2320200400071 COMMON 13 9 2320200400072 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2320200400073 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 ERR-12 2320200400074 ERR-13 2320200400075 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2320200400076 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2320200400077 PER-CENT 2320200400078 0.96 2.51 0.01 0.06 0.36 3.86 2320200400079 0.4 0.39 1.92 0.01 0.004 0.30 2320200400080 0.1 2320200400081 ENDCOMMON 9 0 2320200400082 DATA 6 1 2320200400083 EN DATA ERR-T ERR-T MONIT MONIT-ERR 2320200400084 EV B B PER-CENT B PER-CENT 2320200400085 0.0253 2.51 0.13 4.73 13.3 0.75 2320200400086 ENDDATA 3 0 2320200400087 ENDSUBENT 86 0 2320200499999 SUBENT 23202005 20131114 22372320200500001 BIB 9 97 2320200500002 REACTION (60-ND-148(N,G)60-ND-149,,RI) 2320200500003 SAMPLE Nd(2)O(3) powder, purity > 99.99%, from Aldrich corp. 2320200500004 Mixed with Al(2)O(3) powder as (91.5% Al(2)O(3) + 2320200500005 8.5% Nd(2)O(3)) and (96.6% Al(2)O(3) + 3.4% MnO(2)) to 2320200500006 minimize errors due to self-shielding effect. 2320200500007 Each of the samples of MnO(2) and Nd(2)O(3) was 2320200500008 thoroughly mixed in an agate independently with using 2320200500009 Al(2)O(3) fine powder.Then ten diluted Nd-samples 2320200500010 having each mass of about 0.8 g were individually 2320200500011 filled in polystyrene tubes with height/diameter about 2320200500012 2 and 1 mm wall thickness. Five of them were used for 2320200500013 Cd-covered irradiation and other five - for obtaining 2320200500014 bare irradiation data. The same sample preparation 2320200500015 procedure was employed for ten Mn samples. 2320200500016 (60-ND-148,NAT=0.05756) Isotopic abundance 2320200500017 5.756+-0.021% . 2320200500018 (25-MN-55,NAT=1.00) 2320200500019 DECAY-DATA (60-ND-149,1.728HR,DG,211.309,0.259) 2320200500020 1.728+-0.001 hr, 211.309+-0.007 keV, 25.9+-1.0 % . 2320200500021 MONITOR ((MONIT1)25-MN-55(N,G)25-MN-56,,RI) Main monitor. 2320200500022 14.0+-0.3 b. 2320200500023 ((MONIT2)25-MN-55(N,G)25-MN-56,,SIG) Thermal c-s. 2320200500024 13.3+-0.1 b. 2320200500025 DECAY-MON (25-MN-56,2.5789HR,DG,846.754,0.989) 2320200500026 2.5789+-0.0001 hr, 846.754+-0.020 keV, 98.9+-0.3 % . 2320200500027 DETECTOR (HPGE) Coaxial n-type HPGe detector (Canberra GR2020) 2320200500028 to measure induced activity. Active volume about 2320200500029 100 cm**3. Measured relative efficiency of 22.6% at 2320200500030 1332.5 keV of 60Co, energy resolution 1.80 keV, 2320200500031 peak-to-Compton ratio of 53.5:1 at 1332.5 keV of 60Co. 2320200500032 Shielded by a 10 cm thick lead lined with 1 mm copper 2320200500033 sheets on all sides. 2320200500034 The gamma detection efficiency as a function of energy 2320200500035 was determined using the powder radioactive standard 2320200500036 containing a mixture of 241Am, 109Cd, 57Co, 123mTe, 2320200500037 51Cr, 113Sn, 85Sr, 137Cs, 60Co, 88Y radionuclides. 2320200500038 The samples were counted on the end-cap of detector. 2320200500039 ANALYSIS Westcott correction factors g(20 degC) 1.0004 for 148Nd2320200500040 and 1.0003 for 55Mn isotopes. 2320200500041 Neutron self-shielding factors for diluted MnO(2)and 2320200500042 Nd(2)O(3) samples: 2320200500043 Mn - 0.997 for thermal neutrons, 0.903- epithermal; 2320200500044 Nd - 0.991 for thermal neutrons, 0.928- epithermal; 2320200500045 were estimated by the simplified procedure taking into 2320200500046 account the necessary nuclear data such as resonance 2320200500047 parameter, absorption, scattering and total microscopic2320200500048 cross-sections, which are taken from JENDL-4.0 and 2320200500049 ENDF/B-VII online data libraries. 2320200500050 Correction factor for gamma ray attenuation 2320200500051 for Mn - 1.010, for Nd - 1.038. 2320200500052 True coincidence effects are cancelled out each other 2320200500053 when Cd-ratios are used in the resonance integral 2320200500054 determinations. 2320200500055 Effective resonance energy for Mn - 468+-51 eV, 2320200500056 for Nd - 236. eV . 2320200500057 ERR-ANALYS Uncertainties due to: 2320200500058 (ERR-1) Alpha - shape parameter 3.28%. 2320200500059 (ERR-2) Cadmium cut-off energy 0.45%. 2320200500060 (ERR-3) Cadmium ratio of 56Mn 1.66%. 2320200500061 (ERR-4) Cadmium ratio of 149Nd 4.86%. 2320200500062 (ERR-5) Thermal neutron self-shielding factor for Mn 2320200500063 sample 0.10%. 2320200500064 (ERR-6) Thermal neutron self-shielding factor for Nd 2320200500065 sample 0.40%. 2320200500066 (ERR-7) Epithermal neutron self-shielding factor for Mn2320200500067 sample 0.20%. 2320200500068 (ERR-8) Epithermal neutron self-shielding factor for Nd2320200500069 sample 2.00%. 2320200500070 (ERR-9) Reference resonance integral cross-section of 2320200500071 55Mn 1.73%. 2320200500072 (ERR-10) Reference thermal neutron cross section of 2320200500073 55Mn 0.61%. 2320200500074 (ERR-11) Reference thermal neutron cross section of 2320200500075 148Nd 5.18%. 2320200500076 (ERR-12) Effective resonance energy of 55Mn 0.44%. 2320200500077 (ERR-13) Effective resonance energy of 149Nd 1.05%. 2320200500078 (ERR-T) Total uncertainty, 8.55%. 2320200500079 Relative uncertainties on the resonance integral value 2320200500080 were defined by relative uncertainty multiplied by 2320200500081 propagation factor : 2320200500082 Relative uncertainty,% Propagation factor 2320200500083 ERR-1 19.3 0.17 2320200500084 ERR-2 15. 0.03 2320200500085 ERR-3 0.6 1.04 2320200500086 ERR-4 3.8 1.28 2320200500087 ERR-5 0.1 1.00 2320200500088 ERR-6 0.4 1.00 2320200500089 ERR-7 0.2 1.00 2320200500090 ERR-8 2. 1.00 2320200500091 ERR-9 2.14 0.81 2320200500092 ERR-10 0.75 0.81 2320200500093 ERR-11 5.18 1.00 2320200500094 ERR-12 10.9 0.804 2320200500095 ERR-13 15. 0.07 2320200500096 STATUS (TABLE) Table 3 of J,ANE,62,274,2013 . 2320200500097 Uncertainties - Table 5. 2320200500098 (DEP,23202004) Nd-148 n,g thermal c-s used to drive RI.2320200500099 ENDBIB 97 0 2320200500100 COMMON 13 9 2320200500101 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2320200500102 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 ERR-12 2320200500103 ERR-13 2320200500104 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2320200500105 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2320200500106 PER-CENT 2320200500107 3.28 0.45 1.66 4.86 0.10 0.40 2320200500108 0.20 2.00 1.73 0.61 5.18 0.44 2320200500109 1.05 2320200500110 ENDCOMMON 9 0 2320200500111 DATA 6 1 2320200500112 EN-MIN DATA ERR-T ERR-T MONIT1 MONIT2 2320200500113 EV B B PER-CENT B B 2320200500114 0.55 14.6 1.3 8.55 14.0 13.3 2320200500115 ENDDATA 3 0 2320200500116 ENDSUBENT 115 0 2320200599999 SUBENT 23202006 20131114 22372320200600001 BIB 9 70 2320200600002 REACTION (55-CS-133(N,G)55-CS-134-M,,SIG) 2320200600003 SAMPLE Cs(2)CO(3) powder, purity > 99.99%, from Aldrich corp.2320200600004 Mixed with Al(2)O(3) powder as (96.3% Al(2)O(3) + 2320200600005 3.7% Cs(2)CO(3)) and (96.6% Al(2)O(3) + 3.4% MnO(2)) to2320200600006 minimize errors due to self-shielding effect. 2320200600007 The diluted samples were filled in small polystyrene 2320200600008 tubes with the 6.5 mm diameter, 13.1 mm height, 1 mm 2320200600009 wall thickness. Ten diluted Cs-samples having each mass2320200600010 of about 0.8 g were individually prepared. Five them 2320200600011 were used for Cd-covered irradiation and the other five2320200600012 samples were used for obtaining bare irradiation data. 2320200600013 The same sample preparation produces were employed for 2320200600014 ten Mn samples. 2320200600015 (55-CS-133,NAT=1.00) 2320200600016 (25-MN-55,NAT=1.00) 2320200600017 DECAY-DATA (55-CS-134-M,2.912HR,DG,127.502,0.126) 2320200600018 2.912+-0.002 hr, 127.502+-0.003 keV, 12.6+-0.4 % . 2320200600019 MONITOR (25-MN-55(N,G)25-MN-56,,SIG) 13.3+-0.1 b. 2320200600020 DECAY-MON (25-MN-56,2.5789HR,DG,846.754,0.989) 2320200600021 2.5789+-0.0001 hr, 846.754+-0.020 keV, 98.9+-0.3 % . 2320200600022 DETECTOR (HPGE) Coaxial n-type HPGe detector (Canberra GR2020) 2320200600023 to measure induced activity. Active volume about 2320200600024 100 cm**3. Measured relative efficiency of 22.6% at 2320200600025 1332.5 keV of 60Co, energy resolution 1.80 keV, 2320200600026 peak-to-Compton ratio of 53.5:1 at 1332.5 keV of 60Co. 2320200600027 Shielded by a 10 cm thick lead lined with 1 mm copper 2320200600028 sheets on all sides. 2320200600029 The gamma detection efficiency as a function of energy 2320200600030 was determined using the multi-nuclide standard source 2320200600031 EG-ML S/N:1160-39-3 in sand matrix (SiO2: 1.7 +- 0.1 2320200600032 g/cm**33) spiked with 241Am, 109Cd, 57Co, 123mTe, 51Cr,2320200600033 113Sn, 85Sr, 137Cs, 60Co, 88Y radionuclides. 2320200600034 The samples were counted on the end-cap of detector. 2320200600035 The counting times varied between 2 and 8 h, depending 2320200600036 mainly on the activity level of 134mCs or 56Mn products2320200600037 in the samples. 2320200600038 ANALYSIS Westcott correction factors g(20 degC) 1.0030 for 133Cs2320200600039 and 1.0003 for 55Mn isotopes were used in analysis. 2320200600040 Calculated neutron self-shielding factors for diluted 2320200600041 MnO(2)and Cs(2)CO(3) samples: 2320200600042 Mn - 0.997 for thermal neutrons, 2320200600043 Cs - 0.998 for thermal neutrons. 2320200600044 Correction factor for gamma ray attenuation 2320200600045 for Mn - 1.010, for Cs - 1.046. 2320200600046 True coincidence summing factor 2320200600047 for Mn - 0.963, for Cs - 0.999 . 2320200600048 ERR-ANALYS Uncertainties due to: 2320200600049 (ERR-1) Peak area for Cs 1.15% , based on counting 2320200600050 statistics of +-1.65sigma. 2320200600051 (ERR-2) Detection efficiency for Cs 2.50% 2320200600052 (ERR-3) Mass of Cs sample 0.01% 2320200600053 (ERR-4) Half-life for Cs 0.07% 2320200600054 (ERR-5) Gamma-ray emission probability for Cs 3.17% 2320200600055 (ERR-6) Thermal neutron self-shielding factor for Cs 2320200600056 0.5% 2320200600057 (ERR-7) g(20 degC) - Westcott Factor for Cs 0.5% 2320200600058 (ERR-8) Peak area for Mn 0.39% , based on counting 2320200600059 statistics of +-1.65sigma. 2320200600060 (ERR-9) Detection efficiency for Mn 2.75% 2320200600061 (ERR-10) Mass of Mn sample 0.01% 2320200600062 (ERR-11) Half-life for Mn 0.004% 2320200600063 (ERR-12) Gamma-ray emission probability for Mn 0.30% 2320200600064 (ERR-13) Thermal neutron self-shielding factor for Mn 2320200600065 0.1% 2320200600066 (ERR-14) g(20 degC) - Westcott Factor for Mn 0.5% 2320200600067 (MONIT-ERR) Monitor thermal neutron cross section 0.75%2320200600068 Total uncertainty for Mn 2.94% . 2320200600069 (ERR-T) Total uncertainty 4.26% =0.14 b. 2320200600070 STATUS (TABLE) Table 3 of J,ANE,62,178,2013 . 2320200600071 Uncertainties - Table 4. 2320200600072 ENDBIB 70 0 2320200600073 COMMON 14 9 2320200600074 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2320200600075 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 ERR-12 2320200600076 ERR-13 ERR-14 2320200600077 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2320200600078 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2320200600079 PER-CENT PER-CENT 2320200600080 1.15 2.50 0.01 0.07 3.17 0.5 2320200600081 0.5 0.39 2.75 0.01 0.004 0.30 2320200600082 0.1 0.5 2320200600083 ENDCOMMON 9 0 2320200600084 DATA 6 1 2320200600085 EN DATA ERR-T ERR-T MONIT MONIT-ERR 2320200600086 EV B B PER-CENT B PER-CENT 2320200600087 0.0253 2.77 0.14 4.26 13.3 0.75 2320200600088 ENDDATA 3 0 2320200600089 ENDSUBENT 88 0 2320200699999 SUBENT 23202007 20131114 22372320200700001 BIB 9 97 2320200700002 REACTION (55-CS-133(N,G)55-CS-134-M,,RI) 2320200700003 SAMPLE Cs(2)CO(3) powder, purity > 99.99%, from Aldrich corp.2320200700004 Mixed with Al(2)O(3) powder as (96.3% Al(2)O(3) + 2320200700005 3.7% Cs(2)CO(3)) and (96.6% Al(2)O(3) + 3.4% MnO(2)) to2320200700006 minimize errors due to self-shielding effect. 2320200700007 The diluted samples were filled in small polystyrene 2320200700008 tubes with the 6.5 mm diameter, 13.1 mm height, 1 mm 2320200700009 wall thickness. Ten diluted Cs-samples having each mass2320200700010 of about 0.8 g were individually prepared. Five them 2320200700011 were used for Cd-covered irradiation and the other five2320200700012 samples were used for obtaining bare irradiation data. 2320200700013 The same sample preparation produces were employed for 2320200700014 ten Mn samples. 2320200700015 (55-CS-133,NAT=1.00) 2320200700016 (25-MN-55,NAT=1.00) 2320200700017 DECAY-DATA (55-CS-134-M,2.912HR,DG,127.502,0.126) 2320200700018 2.912+-0.002 hr, 127.502+-0.003 keV, 12.6+-0.4 % . 2320200700019 MONITOR ((MONIT1)25-MN-55(N,G)25-MN-56,,RI) Main monitor. 2320200700020 14.0+-0.3 b. 2320200700021 ((MONIT2)25-MN-55(N,G)25-MN-56,,SIG) Thermal c-s. 2320200700022 13.3+-0.1 b. 2320200700023 DECAY-MON (25-MN-56,2.5789HR,DG,846.754,0.989) 2320200700024 2.5789+-0.0001 hr, 846.754+-0.020 keV, 98.9+-0.3 % . 2320200700025 DETECTOR (HPGE) Coaxial n-type HPGe detector (Canberra GR2020) 2320200700026 to measure induced activity. Active volume about 2320200700027 100 cm**3. Measured relative efficiency of 22.6% at 2320200700028 1332.5 keV of 60Co, energy resolution 1.80 keV, 2320200700029 peak-to-Compton ratio of 53.5:1 at 1332.5 keV of 60Co. 2320200700030 Shielded by a 10 cm thick lead lined with 1 mm copper 2320200700031 sheets on all sides. 2320200700032 The gamma detection efficiency as a function of energy 2320200700033 was determined using the multi-nuclide standard source 2320200700034 EG-ML S/N:1160-39-3 in sand matrix (SiO2: 1.7 +- 0.1 2320200700035 g/cm**33) spiked with 241Am, 109Cd, 57Co, 123mTe, 51Cr,2320200700036 113Sn, 85Sr, 137Cs, 60Co, 88Y radionuclides. 2320200700037 The samples were counted on the end-cap of detector. 2320200700038 The counting times varied between 2 and 8 h, depending 2320200700039 mainly on the activity level of 134mCs or 56Mn products2320200700040 in the samples. 2320200700041 ANALYSIS Westcott correction factors g(20 degC) 1.0030 for 133Cs2320200700042 and 1.0003 for 55Mn isotopes were used in analysis. 2320200700043 Calculated neutron self-shielding factors for diluted 2320200700044 MnO(2)and Cs(2)CO(3) samples: 2320200700045 Mn - 0.997 for thermal neutrons, 0.903 for epithermal, 2320200700046 Cs - 0.998 for thermal neutrons, 0.901 for epithermal. 2320200700047 Correction factor for gamma ray attenuation 2320200700048 for Mn - 1.010, for Cs - 1.046. 2320200700049 True coincidence summing factor 2320200700050 for Mn - 0.963, for Cs - 0.999 . 2320200700051 Effective resonance energy for Mn - 468+-51 eV, 2320200700052 for Cs - 9.27+-1.02 eV . 2320200700053 ERR-ANALYS Uncertainties due to: 2320200700054 (ERR-1) Alpha - shape parameter 0.97%. 2320200700055 (ERR-2) Cadmium cut-off energy 0.60%. 2320200700056 (ERR-3) Cadmium ratio of 56Mn 1.71%. 2320200700057 (ERR-4) Cadmium ratio of 134Cs 4.40%. 2320200700058 (ERR-5) Thermal neutron self-shielding factor for Mn 2320200700059 sample 0.10%. 2320200700060 (ERR-6) Thermal neutron self-shielding factor for Cs 2320200700061 sample 0.50%. 2320200700062 (ERR-7) Epithermal neutron self-shielding factor for Mn2320200700063 sample 0.50%. 2320200700064 (ERR-8) Epithermal neutron self-shielding factor for Cs2320200700065 sample 0.20%. 2320200700066 (ERR-9) Reference resonance integral cross-section of 2320200700067 55Mn 1.80%. 2320200700068 (ERR-10) Reference thermal neutron cross section of 2320200700069 55Mn 0.63%. 2320200700070 (ERR-11) Reference thermal neutron cross section of 2320200700071 133Cs 5.18%. 2320200700072 (ERR-12) g-Westcott factor of 55Mn 0.42% 2320200700073 (ERR-13) g-Westcott factor of 133Cs 0.50% 2320200700074 (ERR-14) Effective resonance energy of 55Mn 0.44%. 2320200700075 (ERR-15) Effective resonance energy of 133Cs 0.88%. 2320200700076 (ERR-T) Total uncertainty, 7.53%. 2320200700077 Relative uncertainties on the resonance integral value 2320200700078 were defined by relative uncertainty multiplied by 2320200700079 propagation factor : 2320200700080 Relative uncertainty,% Propagation factor 2320200700081 ERR-1 19.3 0.05 2320200700082 ERR-2 15. 0.04 2320200700083 ERR-3 1.6 1.07 2320200700084 ERR-4 2.8 1.57 2320200700085 ERR-5 0.1 1.00 2320200700086 ERR-6 0.5 1.00 2320200700087 ERR-7 0.2 1.00 2320200700088 ERR-8 1. 1.00 2320200700089 ERR-9 2.14 0.84 2320200700090 ERR-10 0.75 0.84 2320200700091 ERR-11 5.18 1.00 2320200700092 ERR-12 0.5 0.84 2320200700093 ERR-13 0.5 1.00 2320200700094 ERR-14 10.9 0.04 2320200700095 ERR-15 11. 0.08 2320200700096 STATUS (TABLE) Table 3 of J,ANE,62,178,2013 . 2320200700097 Uncertainties - Table 5. 2320200700098 (DEP,23202006) Cs-133 n,g thermal c-s used to drive RI.2320200700099 ENDBIB 97 0 2320200700100 COMMON 15 9 2320200700101 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2320200700102 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 ERR-12 2320200700103 ERR-13 ERR-14 ERR-15 2320200700104 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2320200700105 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2320200700106 PER-CENT PER-CENT PER-CENT 2320200700107 0.97 0.60 1.71 4.40 0.10 0.50 2320200700108 0.20 1.00 1.80 0.63 5.18 0.42 2320200700109 0.50 0.44 0.88 2320200700110 ENDCOMMON 9 0 2320200700111 DATA 6 1 2320200700112 EN-MIN DATA ERR-T ERR-T MONIT1 MONIT2 2320200700113 EV B B PER-CENT B B 2320200700114 0.55 22.8 1.7 7.53 14.0 13.3 2320200700115 ENDDATA 3 0 2320200700116 ENDSUBENT 115 0 2320200799999 ENDENTRY 7 0 2320299999999