ENTRY 30906 20090912 31413090600000001 SUBENT 30906001 20090912 31413090600100001 BIB 11 30 3090600100002 TITLE Measurements of the total neutron cross-section of 3090600100003 cerium and thulium in the energy range from 3090600100004 1.8 milli-eV to 1.8 eV 3090600100005 AUTHOR (M.Adib,R.M.A.Maayouf,A.Abdel-Kawy,F.Abu-Elnour, 3090600100006 I.Hamouda) 3090600100007 INSTITUTE (3EGYCAI) 3090600100008 REFERENCE (J,AKE,33,(3),212,1979) Experimental details given 3090600100009 (C,79BOLOGN,,95,197912) Similar to journal 3090600100010 Atomkernenergie/Kerntechnik vol. 33, No 2, 1979, p.2123090600100011 SAMPLE Samples were prepared from spec. pure fine oxide 3090600100012 powders, Ce02 and Tm203, packed in perspex containers. 3090600100013 Spectroscopic analysis for Ce was: Fe: 5ppm, Na: 1ppm, 3090600100014 Cu: < 1ppm, Mg: 1 ppm, Ag: < 1ppm, 3090600100015 one sample of thickness 5.11 g/cm2 was prepared. 3090600100016 Spectroscopic analysis for Tm was: Ca: 1ppm, Si: 2ppm, 3090600100017 Fe: 5ppm, Na : 1ppm and Mg: < 1ppm. One 3090600100018 sample of thickness 1.23 g/cm2 was prepared. 3090600100019 Ce02 crystallizes in a cubic system related to the 3090600100020 space group F(M)3(M) - 5 O (H). 3090600100021 MONITOR Absolute measurement 3090600100022 FACILITY (REAC,3EGYCAI) Thermal reactor ET-RR-1 3090600100023 METHOD (TOF) The spectrometer resolution at a flight path of 3090600100024 5.66 m and rotor speeds of 1415 rpm and 2880 rpm 3090600100025 is 23 microsec/m and 11 microsec/m. 3090600100026 DETECTOR No further information 3090600100027 ERR-ANALYS (DATA-ERR) No description of error analysis. 3090600100028 HISTORY (19890508C) TMK,VOF 3090600100029 (19930126A) HW.-Alterations in subents 002-005,007,008.3090600100030 (20090912A) SD:Updated to new date formats,lower case. 3090600100031 Data digitized from figs.2,3. Subent 10 was added. 3090600100032 ENDBIB 30 0 3090600100033 NOCOMMON 0 0 3090600100034 ENDSUBENT 33 0 3090600199999 SUBENT 30906002 20090912 31413090600200001 BIB 5 12 3090600200002 REACTION (58-CE-0(N,TOT),,SIG) 3090600200003 ANALYSIS The total neutron cross section was obtained from the 3090600200004 total neutron cross section of CeO2 by subtraction of 3090600200005 the oxygen cross section incoherently. 3090600200006 ERR-ANALYS (ERR-DIG) Digitizing error 3090600200007 STATUS (CURVE) Data were digitized from fig.2 in 3090600200008 Atomkernenergie/Kerntechnik vol. 33, No 3, 1979, p.212.3090600200009 HISTORY (19930126A) HW.-'Deriv' added to reaction SF9, EN-MIN 3090600200010 altered in data section, explanation of how data has 3090600200011 been derived given in comment.- 3090600200012 (20090912A) SD: Data were digitized from fig.2. 3090600200013 'DERIV' was deleted. 3090600200014 ENDBIB 12 0 3090600200015 COMMON 1 3 3090600200016 ERR-DIG 3090600200017 B 3090600200018 0.1 3090600200019 ENDCOMMON 3 0 3090600200020 DATA 3 169 3090600200021 WVE-LN DATA DATA-ERR 3090600200022 ANGSTROM B B 3090600200023 0.0094 10.87 0.55 3090600200024 0.0148 10.86 3090600200025 0.0179 11.32 3090600200026 0.0218 11.13 3090600200027 0.0248 10.94 3090600200028 0.0287 11.22 3090600200029 0.0333 10.85 3090600200030 0.0356 11.30 3090600200031 0.0387 11.57 3090600200032 0.0464 11.39 3090600200033 0.0487 11.29 3090600200034 0.0511 11.84 3090600200035 0.0534 11.10 3090600200036 0.0549 11.75 3090600200037 0.0596 12.29 3090600200038 0.0634 11.83 3090600200039 0.0673 12.19 3090600200040 0.0703 11.82 3090600200041 0.0742 12.10 3090600200042 0.0773 11.91 3090600200043 0.0796 12.28 3090600200044 0.0827 11.91 3090600200045 0.0865 12.27 3090600200046 0.0896 11.99 3090600200047 0.0935 12.36 3090600200048 0.0989 12.44 3090600200049 0.1020 12.26 3090600200050 0.1035 12.81 3090600200051 0.1074 12.53 3090600200052 0.1128 12.71 3090600200053 0.1166 12.34 3090600200054 0.1205 12.79 3090600200055 0.1259 12.70 3090600200056 0.1297 12.97 3090600200057 0.1328 12.78 3090600200058 0.1351 12.32 3090600200059 0.1359 13.15 3090600200060 0.1405 13.14 3090600200061 0.1459 13.32 3090600200062 0.1482 12.86 3090600200063 0.1505 12.58 3090600200064 0.1544 12.40 3090600200065 0.1559 12.86 3090600200066 0.1605 12.76 3090600200067 0.1621 13.22 3090600200068 0.1652 12.94 3090600200069 0.1660 13.49 3090600200070 0.1691 13.85 3090600200071 0.1714 13.39 3090600200072 0.1736 12.93 3090600200073 0.1767 13.30 3090600200074 0.1791 13.66 3090600200075 0.1822 13.93 3090600200076 0.1860 14.02 3090600200077 0.1899 13.56 3090600200078 0.1922 14.11 3090600200079 0.1976 14.01 3090600200080 0.1976 14.56 3090600200081 0.2015 14.83 3090600200082 0.2045 14.37 3090600200083 0.2061 15.29 3090600200084 0.2069 15.84 3090600200085 0.2108 15.56 3090600200086 0.2131 16.20 3090600200087 0.2162 16.29 3090600200088 0.2193 16.74 3090600200089 0.2193 15.92 3090600200090 0.2200 15.46 3090600200091 0.2215 15.19 3090600200092 0.2222 13.90 3090600200093 0.2223 14.63 3090600200094 0.2238 14.27 3090600200095 0.2277 14.26 3090600200096 0.2315 14.81 3090600200097 0.2331 14.44 3090600200098 0.2346 13.89 3090600200099 0.2369 14.16 3090600200100 0.2384 14.44 3090600200101 0.2385 14.90 3090600200102 0.2416 15.26 3090600200103 0.2447 15.17 3090600200104 0.2477 14.98 3090600200105 0.2500 15.25 3090600200106 0.2524 15.53 3090600200107 0.2547 16.07 3090600200108 0.2586 16.53 3090600200109 0.2617 16.89 3090600200110 0.2656 17.44 3090600200111 0.2679 17.71 3090600200112 0.2710 17.99 3090600200113 0.2748 16.70 3090600200114 0.2779 17.06 3090600200115 0.2802 17.61 3090600200116 0.2856 17.61 3090600200117 0.2887 18.34 3090600200118 0.2926 18.61 3090600200119 0.2950 19.71 3090600200120 0.2996 19.52 3090600200121 0.3027 20.44 3090600200122 0.3058 20.80 3090600200123 0.3089 21.35 3090600200124 0.3090 21.80 3090600200125 0.3097 20.98 3090600200126 0.3129 22.53 3090600200127 0.3167 22.17 3090600200128 0.3198 22.80 3090600200129 0.3229 23.26 3090600200130 0.3260 23.99 3090600200131 0.3276 23.53 3090600200132 0.3298 23.16 3090600200133 0.3314 23.80 3090600200134 0.3376 24.44 3090600200135 0.3385 25.54 3090600200136 0.3423 26.09 3090600200137 0.3455 26.82 3090600200138 0.3501 27.36 3090600200139 0.3525 28.37 3090600200140 0.3594 28.45 3090600200141 0.3656 29.18 3090600200142 0.3726 30.18 3090600200143 0.3794 27.25 3090600200144 0.3796 31.65 3090600200145 0.3868 21.93 3090600200146 0.3938 23.02 3090600200147 0.4007 23.20 3090600200148 0.4069 24.02 3090600200149 0.4139 25.02 3090600200150 0.4201 25.56 3090600200151 0.4279 26.29 3090600200152 0.4348 27.02 3090600200153 0.4410 27.75 3090600200154 0.4488 28.38 3090600200155 0.4550 29.94 3090600200156 0.4620 30.48 3090600200157 0.4682 31.85 3090600200158 0.4752 32.58 3090600200159 0.4830 33.40 3090600200160 0.4892 34.31 3090600200161 0.4962 35.86 3090600200162 0.5047 36.40 3090600200163 0.5101 36.12 3090600200164 0.5163 37.22 3090600200165 0.5240 37.30 3090600200166 0.5302 38.21 3090600200167 0.5371 37.66 3090600200168 0.5440 36.74 3090600200169 0.5510 37.74 3090600200170 0.5579 37.92 3090600200171 0.5657 39.38 3090600200172 0.5720 41.57 3090600200173 0.5782 40.92 3090600200174 0.5853 43.76 3090600200175 0.5921 41.65 3090600200176 0.5992 44.48 3090600200177 0.6052 42.92 3090600200178 0.6115 45.39 3090600200179 0.6188 50.97 0.73 3090600200180 0.6193 45.66 1.10 3090600200181 0.6242 51.06 0.82 3090600200182 0.6249 49.14 1.28 3090600200183 0.6268 41.99 3090600200184 0.6273 51.15 0.92 3090600200185 0.6336 40.97 3090600200186 0.6398 41.61 3090600200187 0.6476 43.53 3090600200188 0.6530 43.16 3090600200189 0.6609 45.81 3090600200190 0.6671 46.53 3090600200191 0.6732 45.34 3090600200192 ENDDATA 171 0 3090600200193 ENDSUBENT 192 0 3090600299999 SUBENT 30906003 20090912 31413090600300001 BIB 4 8 3090600300002 REACTION (58-CE-0(N,TOT),,SIG,,,DERIV) 3090600300003 COMMENT Given data is in reasonable agreement with the value 3090600300004 (4.7 +- 0.3) b of Vertebnii, V.P.,et al.: IAEA second 3090600300005 Int. Conf. on Nucl. Data for Reactors, Helsinki,1970. 3090600300006 STATUS (DEP,30906002) 3090600300007 (TABLE) Data from the text of AKE,33,212,1979 3090600300008 HISTORY (19930126A) HW.-Modifier 'MXW' removed from SF8 in 3090600300009 reaction code, 'EN' changed in common section.- 3090600300010 ENDBIB 8 0 3090600300011 COMMON 1 3 3090600300012 EN 3090600300013 EV 3090600300014 0.025 3090600300015 ENDCOMMON 3 0 3090600300016 DATA 2 1 3090600300017 DATA DATA-ERR 3090600300018 B B 3090600300019 5.28 0.30 3090600300020 ENDDATA 3 0 3090600300021 ENDSUBENT 20 0 3090600399999 SUBENT 30906004 20090912 31413090600400001 BIB 4 18 3090600400002 REACTION (58-CE-0(N,EL)58-CE-0,POT,SIG,,,DERIV) 3090600400003 COMMENT Given data was calculated using the tabulated form 3090600400004 factors reported by Blume,M., et al. : J. Chem. Phys. 3090600400005 37 (1962) 1245 and Blume,M., et al. : J. Chem. Phys. 3090600400006 41 (1964) 1878 and incoherently subtracted from the 3090600400007 obtained value of the total neutron cross-section. 3090600400008 Fig. of potential scattering cross-section vs. neutron 3090600400009 wave length and energy range of 1.8 eV to 0.02 eV is 3090600400010 given in Jour. of Atomkernenergie/Kerntechnik vol. 33, 3090600400011 No. 3. 1979, p. 212. This value was found to fluctuate 3090600400012 near constant value of given data. 3090600400013 This value is in good agreement with the value of 3090600400014 (2.92 +- 0.05) b of Hughes,D.J., R.Schwartz: Neutron 3090600400015 Cross-Sections, BNL - 325, Supplement no. 2 (1966) 3090600400016 and Supplement (1975) 3090600400017 STATUS (DEP,30906002) 3090600400018 (TABLE) Data from the text of AKE,33,212,1979 3090600400019 HISTORY (19930126A) HW.- EN-MIN in common section altered.- 3090600400020 ENDBIB 18 0 3090600400021 COMMON 2 3 3090600400022 EN-MIN EN-MAX 3090600400023 EV EV 3090600400024 0.02 1.8 3090600400025 ENDCOMMON 3 0 3090600400026 DATA 2 1 3090600400027 DATA DATA-ERR 3090600400028 B B 3090600400029 3.1 0.3 3090600400030 ENDDATA 3 0 3090600400031 ENDSUBENT 30 0 3090600499999 SUBENT 30906005 20090912 31413090600500001 BIB 4 12 3090600500002 REACTION (58-CE-0(N,THS)58-CE-0,COH,AMP,,,DERIV) 3090600500003 COMMENT The coherent scattering amplitude was determined from 3090600500004 the Bragg reflections observed in the total neutron 3090600500005 cross section of Ce02. 3090600500006 Given data is in good agreement, within the statistical3090600500007 accuracy, with the value of (4.8 +- 0.06) Fermi of 3090600500008 Hughes, D.J., R.Schwartz: Neutron Cross-Sections, 3090600500009 BNL - 325, Supplement no.2(1966) and Supplement (1975) 3090600500010 STATUS (DEP,30906002) 3090600500011 (TABLE) Data from the text of AKE,33,212,1979 3090600500012 HISTORY (19930126U) HW.-Explanation of how data has been 3090600500013 derived given in comment.- 3090600500014 ENDBIB 12 0 3090600500015 COMMON 2 3 3090600500016 EN-MIN EN-MAX 3090600500017 MILLI-EV EV 3090600500018 1.8 1.8 3090600500019 ENDCOMMON 3 0 3090600500020 DATA 2 1 3090600500021 DATA DATA-ERR 3090600500022 FERMI FERMI 3090600500023 4.8 0.2 3090600500024 ENDDATA 3 0 3090600500025 ENDSUBENT 24 0 3090600599999 SUBENT 30906006 20090912 31413090600600001 BIB 5 7 3090600600002 REACTION (69-TM-169(N,TOT),,SIG) 3090600600003 ERR-ANALYS (ERR-DIG) Digitizing error 3090600600004 COMMENT Fig.3 of cross-section vs. neutron wavelength and 3090600600005 energy range of 1.8 milli-eV to 0.02 eV given in Jour. 3090600600006 Atomkernenergie/Kerntechnik vol. 33, No 3, 1979, p.212.3090600600007 STATUS (CURVE) Data were digitized from fig.3,AKE,33,212,1979 3090600600008 HISTORY (20090912A) SD: Data were digitized from fig.3. 3090600600009 ENDBIB 7 0 3090600600010 COMMON 1 3 3090600600011 ERR-DIG 3090600600012 B 3090600600013 0.8 3090600600014 ENDCOMMON 3 0 3090600600015 DATA 3 158 3090600600016 WVE-LN DATA DATA-ERR 3090600600017 ANGSTROM B B 3090600600018 0.0281 36.14 3090600600019 0.0323 34.43 3090600600020 0.0359 44.21 3090600600021 0.0408 37.58 3090600600022 0.0457 36.69 3090600600023 0.0549 42.29 3090600600024 0.0599 50.41 3090600600025 0.0670 60.14 3090600600026 0.0712 58.43 3090600600027 0.0755 60.83 3090600600028 0.0797 62.40 3090600600029 0.0840 64.80 3090600600030 0.0882 68.01 3090600600031 0.0939 72.02 3090600600032 0.0988 75.23 3090600600033 0.1003 81.76 3090600600034 0.1024 77.63 3090600600035 0.1073 77.56 3090600600036 0.1088 81.63 3090600600037 0.1130 81.57 3090600600038 0.1130 84.85 3090600600039 0.1159 87.26 3090600600040 0.1180 88.87 3090600600041 0.1208 88.83 3090600600042 0.1250 91.22 3090600600043 0.1286 93.63 3090600600044 0.1321 96.85 3090600600045 0.1349 97.63 3090600600046 0.1385 99.21 3090600600047 0.1400 105.75 3090600600048 0.1427 102.43 3090600600049 0.1456 104.84 3090600600050 0.1491 106.43 3090600600051 0.1512 108.04 3090600600052 0.1541 110.45 3090600600053 0.1590 111.20 3090600600054 0.1605 116.09 3090600600055 0.1640 116.04 3090600600056 0.1675 116.81 3090600600057 0.1704 121.68 3090600600058 0.1732 124.10 3090600600059 0.1768 130.60 3090600600060 0.1789 124.83 3090600600061 0.1824 128.88 3090600600062 0.1846 132.12 3090600600063 0.1866 127.17 3090600600064 0.1888 132.06 3090600600065 0.1937 132.80 3090600600066 0.1952 137.70 3090600600067 0.1987 140.10 3090600600068 0.2016 142.52 3090600600069 0.2051 144.10 3090600600070 0.2072 147.35 4.10 3090600600071 0.2093 144.04 3090600600072 0.2128 142.35 3090600600073 0.2137 155.45 3090600600074 0.2150 147.23 3090600600075 0.2171 151.30 3090600600076 0.2193 155.36 3090600600077 0.2213 151.24 3090600600078 0.2235 156.12 3090600600079 0.2243 161.03 3090600600080 0.2264 159.36 3090600600081 0.2292 159.31 3090600600082 0.2327 160.08 3090600600083 0.2362 161.66 3090600600084 0.2398 163.25 3090600600085 0.2433 166.48 3090600600086 0.2469 168.88 3090600600087 0.2476 176.25 3090600600088 0.2511 171.28 3090600600089 0.2547 174.50 3090600600090 0.2575 176.10 3090600600091 0.2603 177.69 3090600600092 0.2631 179.29 3090600600093 0.2660 180.89 3090600600094 0.2688 182.48 3090600600095 0.2710 185.73 3090600600096 0.2738 186.50 3090600600097 0.2766 188.10 3090600600098 0.2780 191.36 3090600600099 0.2830 192.10 3090600600100 0.2837 196.19 3090600600101 0.2859 201.07 3090600600102 0.2886 195.30 3090600600103 0.2908 199.36 3090600600104 0.2957 201.74 3090600600105 0.3000 200.86 3090600600106 0.3028 204.10 3090600600107 0.3050 209.80 3090600600108 0.3099 210.55 3090600600109 0.3128 213.78 3090600600110 0.3163 214.55 3090600600111 0.3184 216.97 3090600600112 0.3192 225.16 3090600600113 0.3213 221.85 3090600600114 0.3233 217.72 3090600600115 0.3255 223.42 3090600600116 0.3283 225.02 3090600600117 0.3305 227.45 3090600600118 0.3340 230.67 3090600600119 0.3368 224.07 3090600600120 0.3404 233.85 3090600600121 0.3433 239.55 3090600600122 0.3475 240.30 3090600600123 0.3504 244.36 3090600600124 0.3526 256.62 8.20 3090600600125 0.3546 242.65 3090600600126 0.3567 245.90 3090600600127 0.3602 246.67 3090600600128 0.3631 251.54 3090600600129 0.3660 259.69 6.56 3090600600130 0.3695 258.82 3090600600131 0.3730 259.59 3090600600132 0.3759 261.18 3090600600133 0.3787 261.96 3090600600134 0.3815 264.38 3090600600135 0.3844 266.79 3090600600136 0.3872 268.39 3090600600137 0.3893 270.82 3090600600138 0.3943 276.48 3090600600139 0.3965 284.64 3090600600140 0.3985 270.68 3090600600141 0.4007 283.76 3090600600142 0.4020 271.44 3090600600143 0.4043 284.52 3090600600144 0.4085 285.28 3090600600145 0.4149 289.28 3090600600146 0.4220 296.55 3090600600147 0.4270 305.49 3090600600148 0.4283 298.91 3090600600149 0.4305 303.80 3090600600150 0.4361 301.25 3090600600151 0.4424 304.44 3090600600152 0.4488 306.80 3090600600153 0.4559 309.15 3090600600154 0.4630 318.88 3090600600155 0.4668 343.41 3090600600156 0.4700 316.31 3090600600157 0.4758 329.34 3090600600158 0.4836 334.96 3090600600159 0.4907 340.59 3090600600160 0.4970 344.59 3090600600161 0.5042 351.86 3090600600162 0.5097 343.58 3090600600163 0.5105 355.86 3090600600164 0.5175 354.11 3090600600165 0.5246 358.11 3090600600166 0.5318 368.65 3090600600167 0.5376 387.42 3090600600168 0.5438 374.21 3090600600169 0.5447 389.77 3090600600170 0.5518 397.86 3090600600171 0.5594 384.63 3090600600172 0.5644 395.21 3090600600173 0.5729 396.72 3090600600174 0.5764 395.84 3090600600175 0.5792 394.16 3090600600176 ENDDATA 160 0 3090600600177 ENDSUBENT 176 0 3090600699999 SUBENT 30906007 20090912 31413090600700001 BIB 4 9 3090600700002 REACTION (69-TM-169(N,TOT),,SIG,,,DERIV) 3090600700003 COMMENT Given data is in agreement with the value of 3090600700004 (134 +- 2) b of Zimmerman,R.L., et al. : Nucl. Phys. 3090600700005 A 95 (1967) 683. 3090600700006 STATUS (DEP,30906006) 3090600700007 (TABLE) Data from the text of AKE,33,212,1979 3090600700008 HISTORY (19930126A) HW.-'MXW' and 'DERIV' removed from reaction3090600700009 code, 'EN' altered in common section.- 3090600700010 (20090920A) OS. DERIV resotred in SF9 3090600700011 ENDBIB 9 0 3090600700012 COMMON 1 3 3090600700013 EN 3090600700014 EV 3090600700015 0.0253 3090600700016 ENDCOMMON 3 0 3090600700017 DATA 2 1 3090600700018 DATA DATA-ERR 3090600700019 B B 3090600700020 126. 6. 3090600700021 ENDDATA 3 0 3090600700022 ENDSUBENT 21 0 3090600799999 SUBENT 30906008 20090912 31413090600800001 BIB 4 8 3090600800002 REACTION (69-TM-169(N,EL)69-TM-169,POT,SIG,,,DERIV) 3090600800003 COMMENT The cross section was determined by calculating the 3090600800004 Paramagnetic cross section and subtracting it incohe- 3090600800005 rently from the total cross section at all energies. 3090600800006 STATUS (DEP,30906006) 3090600800007 (TABLE) Data from the text of AKE,33,212,1979 3090600800008 HISTORY (19930126U) HW.-Explanation of how data has been derive3090600800009 given in comment.- 3090600800010 ENDBIB 8 0 3090600800011 COMMON 2 3 3090600800012 EN-MIN EN-MAX 3090600800013 MILLI-EV EV 3090600800014 1.8 1. 3090600800015 ENDCOMMON 3 0 3090600800016 DATA 2 1 3090600800017 DATA DATA-ERR 3090600800018 B B 3090600800019 7.5 0.7 3090600800020 ENDDATA 3 0 3090600800021 ENDSUBENT 20 0 3090600899999 SUBENT 30906009 20090912 31413090600900001 BIB 4 5 3090600900002 REACTION (69-TM-169(N,ABS),,SIG,,,DERIV) 3090600900003 COMMENT Comment by compiler: data given in abstract only. 3090600900004 STATUS (TABLE) Data taken from Jour. of 3090600900005 Atomkernenergie.Kerntechnik vol. 33, No.3, 1979, p.212.3090600900006 HISTORY (20090920A) OS. DERIV resotred in SF9, EN corrected 3090600900007 ENDBIB 5 0 3090600900008 COMMON 1 3 3090600900009 EN 3090600900010 EV 3090600900011 0.0253 3090600900012 ENDCOMMON 3 0 3090600900013 DATA 2 1 3090600900014 DATA DATA-ERR 3090600900015 B B 3090600900016 89.1 4.1 3090600900017 ENDDATA 3 0 3090600900018 ENDSUBENT 17 0 3090600999999 ENDENTRY 9 0 3090699999999