ENTRY 14113 20061103 13421411300000001 SUBENT 14113001 20061103 13421411300100001 BIB 11 48 1411300100002 INSTITUTE (1USAORU,1USABRK) 1411300100003 REFERENCE (J,PR/C,74,044302,2006) 1411300100004 AUTHOR (M.G.Rios,R.J.Casperson,K.S.Krane,E.B.Norman) 1411300100005 TITLE Neutron capture cross sections of 148Gd and the 1411300100006 decay of 149Gd 1411300100007 FACILITY (REAC,1USAORU) The irradiations were performed in the 1411300100008 TRIGA reactor at Oregon State University. 1411300100009 INC-SOURCE (REAC) Three different irradiation facilities were 1411300100010 used: an in-core irradiation tube (ICIT); a 1411300100011 cadmium-lined in-core irradiation tube (CLICIT), with 1411300100012 a negligible thermal flux (below a cutoff of 0.5 eV) 1411300100013 and the same epithermal flux as the ICIT; and a 1411300100014 thermal column (TC). 1411300100015 DETECTOR (HPGE) The gamma rays were counted using a high purity 1411300100016 Ge (HPGe) detector connected to a digital spectroscopy1411300100017 system. The detector had an active volume of 169 cm3 1411300100018 and a resolution of 1.65 keV for the 1.33-MeV gamma 1411300100019 ray of 60Co (with an efficiency of 35% compared with 1411300100020 NaI). 1411300100021 SAMPLE Radioactive source material of 148Gd (a pure a emitter 1411300100022 with a half-life of 75 yr) was obtained from two 1411300100023 suppliers: Los Alamos National Laboratory and Isotope 1411300100024 Products Laboratory. Both samples were in the form of 1411300100025 a dilute HCl solution. For the cross section 1411300100026 measurements, small quantities of the liquid were 1411300100027 sealed in either polyethylene vials or quartz ampoules1411300100028 for irradiation. In some cases the liquid was 1411300100029 evaporated to dryness prior to irradiation and then 1411300100030 taken up with fresh HCl after irradiation. 1411300100031 In addition to the 149Gd, immediately after the 1411300100032 irradiation our samples contained about 0.7% 152Eu, 1411300100033 0.1% 154Eu, 2% 151Gd, and 0.5% 153Gd. 1411300100034 The samples also contained small amounts of short-lived1411300100035 82Br (produced from neutron activation of Br which is 1411300100036 a contamination in HCl). 1411300100037 METHOD (ACTIV) For the spectroscopic studies of the 149Gd 1411300100038 decay, three different samples were prepared by 1411300100039 irradiating quantities of 148Gd activity each 1411300100040 approximately 103 times stronger than was used for the1411300100041 cross section determinations. 1411300100042 MONITOR For the determination of the neutron fluxes, we used a 1411300100043 variety of flux monitors: 59Co and 197Au in dilute Al 1411300100044 alloys served as primary flux monitors, and 58Fe, 1411300100045 64Zn, and 94,96Zr were used as secondary flux 1411300100046 monitors. All flux monitors were in the form of thin 1411300100047 metal foils of natural isotopic abundances and were 1411300100048 irradiated simultaneously with the 148Gd. 1411300100049 HISTORY (20061103C) DR 1411300100050 ENDBIB 48 0 1411300100051 NOCOMMON 0 0 1411300100052 ENDSUBENT 51 0 1411300199999 SUBENT 14113002 20061103 13421411300200001 BIB 3 3 1411300200002 REACTION (64-GD-148(N,G)64-GD-149,,SIG) 1411300200003 ERR-ANALYS (ERR-T) Total uncertainty 1411300200004 STATUS Data taken from text 1411300200005 ENDBIB 3 0 1411300200006 NOCOMMON 0 0 1411300200007 DATA 3 1 1411300200008 EN-DUMMY DATA ERR-T 1411300200009 EV B B 1411300200010 0.0253 9600. 900. 1411300200011 ENDDATA 3 0 1411300200012 ENDSUBENT 11 0 1411300299999 SUBENT 14113003 20061103 13421411300300001 BIB 3 9 1411300300002 REACTION (64-GD-148(N,G)64-GD-149,,RI) 1411300300003 ERR-ANALYS (ERR-T) The uncertainty in this value is due primarily 1411300300004 to the range of values of the epithermal flux as 1411300300005 determined from the various flux monitors (+/-4%) but 1411300300006 also includes a contribution from the uncertainties in1411300300007 the efficiency of the gamma -ray detector (+/-2%) and 1411300300008 the alpha-particle detector (+/-2%). A net uncertainty1411300300009 of +/-8% is representative of all such contribution 1411300300010 STATUS Data taken from text 1411300300011 ENDBIB 9 0 1411300300012 NOCOMMON 0 0 1411300300013 DATA 3 1 1411300300014 EN-MIN DATA ERR-T 1411300300015 EV B B 1411300300016 0.5 28200. 2300. 1411300300017 ENDDATA 3 0 1411300300018 ENDSUBENT 17 0 1411300399999 SUBENT 14113004 20061103 13421411300400001 BIB 3 4 1411300400002 REACTION (64-GD-148(N,G)64-GD-149,,SPC,,REL) 1411300400003 Intensities normalized to the strongest transitions 1411300400004 ERR-ANALYS (DATA-ERR) No information 1411300400005 STATUS (TABLE) Data taken from table 2 1411300400006 ENDBIB 4 0 1411300400007 COMMON 1 3 1411300400008 EN-DUMMY 1411300400009 EV 1411300400010 0.0253 1411300400011 ENDCOMMON 3 0 1411300400012 DATA 4 77 1411300400013 E E-ERR DATA DATA-ERR 1411300400014 KEV KEV ARB-UNITS ARB-UNITS 1411300400015 82.33 0.08 0.011 0.002 1411300400016 125.99 0.02 0.300 0.006 1411300400017 128.74 0.02 0.081 0.007 1411300400018 132.00 0.01 0.187 0.011 1411300400019 138.10 0.01 0.141 0.008 1411300400020 139.74 0.08 0.029 0.003 1411300400021 149.72 0.01 100.0 0.6 1411300400022 184.50 0.02 0.108 0.003 1411300400023 186.63 0.03 0.024 0.004 1411300400024 213.39 0.08 0.009 0.002 1411300400025 214.28 0.02 0.409 0.011 1411300400026 252.19 0.02 0.563 0.011 1411300400027 260.73 0.03 2.69 0.05 1411300400028 264.60 0.04 0.081 0.004 1411300400029 266.82 0.06 0.036 0.003 1411300400030 272.32 0.03 6.61 0.13 1411300400031 278.34 0.02 0.185 0.006 1411300400032 298.63 0.01 57.9 0.6 1411300400033 302.58 0.03 0.026 0.004 1411300400034 341.66 0.05 0.136 0.017 1411300400035 346.66 0.03 49.8 0.5 1411300400036 349.12 0.10 0.133 0.010 1411300400037 352.79 0.05 0.074 0.009 1411300400038 384.54 0.02 0.154 0.004 1411300400039 398.82 0.03 0.092 0.003 1411300400040 404.32 0.03 0.402 0.005 1411300400041 416.09 0.04 0.048 0.003 1411300400042 418.35 0.04 0.010 0.002 1411300400043 419.47 0.15 0.006 0.002 1411300400044 421.55 0.20 0.010 0.005 1411300400045 431.30 0.02 0.145 0.004 1411300400046 436.24 0.03 0.091 0.004 1411300400047 436.62 0.17 0.043 0.006 1411300400048 456.74 0.04 0.048 0.006 1411300400049 459.84 0.02 1.224 0.022 1411300400050 478.27 0.10 0.047 0.008 1411300400051 478.78 0.02 0.424 0.006 1411300400052 482.66 0.02 0.155 0.003 1411300400053 492.93 0.06 0.034 0.003 1411300400054 496.41 0.02 3.35 0.06 1411300400055 516.57 0.02 5.58 0.10 1411300400056 534.31 0.02 6.49 0.12 1411300400057 552.76 0.02 0.156 0.005 1411300400058 563.58 0.25 0.024 0.004 1411300400059 598.84 0.04 0.047 0.007 1411300400060 601.21 0.03 0.126 0.007 1411300400061 645.31 0.01 3.12 0.04 1411300400062 649.15 0.07 0.033 0.004 1411300400063 662.91 0.01 0.568 0.010 1411300400064 666.29 0.01 1.853 0.022 1411300400065 673.43 0.02 0.0076 0.0012 1411300400066 726.23 0.02 0.168 0.006 1411300400067 734.85 0.03 0.262 0.008 1411300400068 748.62 0.02 17.19 0.20 1411300400069 761.10 0.03 0.017 0.001 1411300400070 776.59 0.05 0.033 0.003 1411300400071 783.45 0.10 0.016 0.002 1411300400072 788.87 0.02 15.11 0.22 1411300400073 798.90 0.02 0.108 0.003 1411300400074 802.91 0.02 0.098 0.003 1411300400075 812.62 0.02 0.305 0.007 1411300400076 842.29 0.10 0.011 0.001 1411300400077 862.87 0.03 0.135 0.002 1411300400078 875.95 0.02 0.320 0.005 1411300400079 933.13 0.02 1.288 0.012 1411300400080 938.63 0.03 5.03 0.04 1411300400081 947.88 0.03 1.99 0.03 1411300400082 952.61 0.03 0.0266 0.0015 1411300400083 992.21 0.04 0.066 0.002 1411300400084 1012.61 0.04 0.0514 0.0011 1411300400085 1015.25 0.09 0.0260 0.0024 1411300400086 1081.57 0.03 0.0356 0.0027 1411300400087 1096.79 0.012 0.005 0.003 1411300400088 1207.58 0.012 0.0030 0.0003 1411300400089 1220.49 0.012 0.0020 0.0003 1411300400090 1231.4 0.2 0.0005 0.0005 1411300400091 1246.27 0.12 0.0046 0.0004 1411300400092 ENDDATA 79 0 1411300400093 ENDSUBENT 92 0 1411300499999 SUBENT 14113005 20061103 13421411300500001 BIB 2 2 1411300500002 REACTION (64-GD-148(N,G)64-GD-149,,SPC,,REL) 1411300500003 STATUS (TABLE) Data taken from table 4 1411300500004 ENDBIB 2 0 1411300500005 COMMON 1 3 1411300500006 EN-DUMMY 1411300500007 EV 1411300500008 0.0253 1411300500009 ENDCOMMON 3 0 1411300500010 DATA 2 34 1411300500011 E DATA-MAX 1411300500012 KEV ARB-UNITS 1411300500013 127.1 0.003 1411300500014 189.7 0.005 1411300500015 196.93 0.01 1411300500016 203.14 0.003 1411300500017 238.25 0.003 1411300500018 239.87 0.003 1411300500019 248.64 0.01 1411300500020 270.79 0.01 1411300500021 292.86 0.01 1411300500022 372.62 0.003 1411300500023 394.59 0.002 1411300500024 400.20 0.002 1411300500025 429.73 0.002 1411300500026 447.42 0.01 1411300500027 502.12 0.002 1411300500028 522.12 0.002 1411300500029 527.92 0.003 1411300500030 574.88 0.002 1411300500031 577.96 0.002 1411300500032 581.79 0.002 1411300500033 590.96 0.002 1411300500034 593.16 0.002 1411300500035 629.01 0.001 1411300500036 672.37 0.001 1411300500037 688.27 0.003 1411300500038 711.72 0.001 1411300500039 715.21 0.001 1411300500040 719.19 0.002 1411300500041 738.66 0.002 1411300500042 756.42 0.003 1411300500043 872.62 0.005 1411300500044 880.04 0.002 1411300500045 898.99 0.001 1411300500046 956.4 0.001 1411300500047 ENDDATA 36 0 1411300500048 ENDSUBENT 47 0 1411300599999 ENDENTRY 5 0 1411399999999