ENTRY 41244 20140814 41644124400000001 SUBENT 41244001 20140814 41644124400100001 BIB 9 25 4124400100002 INSTITUTE (4RUSFEI) 4124400100003 (4UKRIJD) Pilipets. 4CCPIFU at the time of paper 4124400100004 publication 4124400100005 AUTHOR (E.I.Grishanin,G.M.Kukavadze,V.I.Lependin, 4124400100006 L.Ya.Mamelova,I.G.Morozov,V.V.Orlov,D.T.Pilipets) 4124400100007 TITLE Measurement of reactor absorption cross sections of 4124400100008 Gd154 and Gd156 . 4124400100009 REFERENCE (J,AE,22,(2),133,1967) Data for GD-154 and GD-156. 4124400100010 (J,SJA,22,144,1967) Engl.translation of AE,22,133,1967.4124400100011 #doi:10.1007/BF01246280 4124400100012 (J,AE,19,(5),459,1965) Data for Gd-156 are given. 4124400100013 Preliminary publication. 4124400100014 (J,SJA,19,1432,1965) Engl.translation of AE,19,459,19654124400100015 #doi:10.1007/BF01116822 4124400100016 FACILITY (REAC,4UKRIJD) Reactor WWR-M 4124400100017 METHOD (ASEP) Mass-spectrometer MI-1311 to define isotopic 4124400100018 content in activated samples using ions GdO+. 4124400100019 MONITOR Given in proper subentry if available 4124400100020 ERR-ANALYS (DATA-ERR) Errors are not specified 4124400100021 HISTORY (19970428C) + + Compiled at the centre CJD - S.Maev 4124400100022 (19990315U) New dates introduced. References moved 4124400100023 to Subent 41244001 4124400100024 (20140814A) M.M. Upper -> lower case correction. 4124400100025 BIB information was updated. 4124400100026 Refs. of Engl.translations were added. 4124400100027 ENDBIB 25 0 4124400100028 NOCOMMON 0 0 4124400100029 ENDSUBENT 28 0 4124400199999 SUBENT 41244002 20140814 41644124400200001 BIB 8 17 4124400200002 REACTION (64-GD-156(N,G)64-GD-157,,SIG,,MXW) 4124400200003 MONITOR (64-GD-157(N,G)64-GD-158,,SIG,,MXW) 4124400200004 SAMPLE Gadolinium sample with Gd-156 content 94.86 % , 4124400200005 Gd-152 content 0.01 % , Gd-154 content 0.14 % , 4124400200006 Gd-155 content 0.83 % , Gd-157 content 2.93 % , 4124400200007 Gd-158 content 0.89 % , Gd-160 content 0.34 % 4124400200008 INC-SPECT Reactor spectrum. 4124400200009 ANALYSIS Calculated from measured reactor value using 4124400200010 saturated Gd-156/Gd-157 concentration ratio 4124400200011 STATUS (SPSDD,41244004) In AE,22,(2),133,1967 data were 4124400200012 (SPSDD,41244005) re-analyzed. 4124400200013 (PRELM) 4124400200014 (TABLE) Text, page 460 of AE,19,(5),459,1965. 4124400200015 COMMENT .Neutron spectrum temperature in data section corres- 4124400200016 ponds to 400+-30 degree Kelvin 4124400200017 HISTORY (19970428T) * * Converted from SUBENT 80372002 * * 4124400200018 (19990315U) Energy units converted from DEG-K to EV 4124400200019 ENDBIB 17 0 4124400200020 NOCOMMON 0 0 4124400200021 DATA 6 1 4124400200022 EN-MEAN EN-ERR DATA DATA-ERR MONIT MONIT-ERR 4124400200023 EV EV B B B B 4124400200024 3.4500E-02 2.5800E-03 9.8 2.5 150000. 12000. 4124400200025 ENDDATA 3 0 4124400200026 ENDSUBENT 25 0 4124400299999 SUBENT 41244003 20140814 41644124400300001 BIB 5 14 4124400300002 REACTION (64-GD-156(N,G)64-GD-157,,SIG,,,DERIV) 4124400300003 SAMPLE Gadolinium sample with Gd-156 content 94.86 % , 4124400300004 Gd-152 content 0.01 % , Gd-154 content 0.14 % , 4124400300005 Gd-155 content 0.83 % , Gd-157 content 2.93 % , 4124400300006 Gd-158 content 0.89 % , Gd-160 content 0.34 % 4124400300007 ANALYSIS Calculated from reactor value c-s assuming 1/v 4124400300008 Gd-156 sigma dependence. 4124400300009 STATUS (DEP,41244002) 4124400300010 (PRELM) 4124400300011 (TABLE) Text, page 460 of AE,19,(5),459,1965. 4124400300012 HISTORY (19970428T) * * Converted from Subent 80372003 * * 4124400300013 (19990406U) 'SPA' changed to 'MXW' in SF8 4124400300014 (20140814A) M.M. MXW was deleted - C-S at thermal point4124400300015 EN-DUMMY -> EN, DERIV was added in REACTION. 4124400300016 ENDBIB 14 0 4124400300017 NOCOMMON 0 0 4124400300018 DATA 3 1 4124400300019 EN DATA DATA-ERR 4124400300020 MEV B B 4124400300021 2.5000E-08 13. 3. 4124400300022 ENDDATA 3 0 4124400300023 ENDSUBENT 22 0 4124400399999 SUBENT 41244004 20140814 41644124400400001 BIB 7 15 4124400400002 REACTION (64-GD-156(N,G)64-GD-157,,SIG,,SPA) 4124400400003 INC-SPECT Reactor spectrum. 4124400400004 Thermal neutrons integral flux was monitored by 4124400400005 Li6 concentration change. 4124400400006 SAMPLE Enriched Gd-156 sample. Isotopic content, % : 4124400400007 Gd-154 - 0.14+-0.02, Gd-155 - 0.830+-0.017, 4124400400008 Gd-156 - 94.86+-0.11, Gd-157 - 2.93+-0.06, 4124400400009 Gd-158 - 0.89+0.04. 4124400400010 ANALYSIS Calculated from measured reactor value using 4124400400011 saturated Gd-157/Gd-156 concentration ratio 4124400400012 MISC-COL (MISC) Concentrations ratio Gd157 to Gd156 4124400400013 STATUS (COREL,41244002) 4124400400014 (TABLE) Table 2 of AE,22,(2),133,1967. 4124400400015 HISTORY (19970428T) * * Converted from subent 80373004 4124400400016 Energy corrected from 2.35E-8 to 2.53E-8 MEV * * 4124400400017 ENDBIB 15 0 4124400400018 NOCOMMON 0 0 4124400400019 DATA 5 1 4124400400020 EN-DUMMY DATA DATA-ERR MISC MISC-ERR 4124400400021 MEV B B NO-DIM NO-DIM 4124400400022 2.5300E-08 11.5 2.0 7.70E-5 1.30E-5 4124400400023 ENDDATA 3 0 4124400400024 ENDSUBENT 23 0 4124400499999 SUBENT 41244005 20140814 41644124400500001 BIB 7 15 4124400500002 REACTION (64-GD-156(N,G)64-GD-157,,SIG,,SPA) 4124400500003 INC-SPECT Reactor spectrum . 4124400500004 Thermal neutrons integral flux was monitored by 4124400500005 Li6 concentration change. 4124400500006 SAMPLE Natural Gd sample. Isotopic content, %: 4124400500007 Gd-154 - 1.98+-0.05, Gd-155 - 13.03+-0.13, 4124400500008 Gd-156 - 20.71+-0.11, Gd-157 - 15.53+-0.06, 4124400500009 Gd-158 - 24.84+-0.08. 4124400500010 ANALYSIS Calculated from measured reactor value using 4124400500011 saturated Gd-157/Gd-156 concentration ratio 4124400500012 MISC-COL (MISC) Concentrations ratio Gd157 to Gd156 4124400500013 STATUS (TABLE) Table 2 of AE,22,(2),133,1967. 4124400500014 HISTORY (19970428T) * * Converted from SUBENT 80373005 4124400500015 Energy corrected from 2.35E-8 to 2.53E-8 MEV * * 4124400500016 (19990406U) 'MXW' changed to 'SPA' in SF8 4124400500017 ENDBIB 15 0 4124400500018 NOCOMMON 0 0 4124400500019 DATA 5 1 4124400500020 EN-DUMMY DATA DATA-ERR MISC MISC-ERR 4124400500021 MEV B B NO-DIM NO-DIM 4124400500022 2.5300E-08 11.1 2.3 7.42E-3 1.54E-3 4124400500023 ENDDATA 3 0 4124400500024 ENDSUBENT 23 0 4124400599999 SUBENT 41244006 20140814 41644124400600001 BIB 7 14 4124400600002 REACTION (64-GD-154(N,G)64-GD-155,,SIG,,SPA) 4124400600003 INC-SPECT Reactor spectrum. 4124400600004 Thermal neutrons integral flux was monitored by 4124400600005 Li6 concentration change. 4124400600006 SAMPLE Sample enriched to about 66.2 % Gd-154, 4124400600007 Gd-155 - 21.7%, Gd-156 - 5.7%, Gd-157 - 2.3%, 4124400600008 Gd-158 - 2.3 % ( passport data). 4124400600009 ANALYSIS Calculated from measured reactor value using 4124400600010 saturated Gd-155/Gd-154 concentration ratio 4124400600011 MISC-COL (MISC) Concentrations ratio Gd155 to Gd154 4124400600012 STATUS (TABLE) Table 2 of AE,22,(2),133,1967. 4124400600013 HISTORY (19970428T) * * Converted From SUBENT 80373002 4124400600014 Energy corrected from 2.35E-8 to 2.53E-8 MEV * * 4124400600015 (19990406U) 'MXW' changed to 'SPA' in SF8 4124400600016 ENDBIB 14 0 4124400600017 NOCOMMON 0 0 4124400600018 DATA 5 1 4124400600019 EN-DUMMY DATA DATA-ERR MISC MISC-ERR 4124400600020 MEV B B NO-DIM NO-DIM 4124400600021 2.5300E-08 100. 5. 2.80E-3 0.08E-3 4124400600022 ENDDATA 3 0 4124400600023 ENDSUBENT 22 0 4124400699999 SUBENT 41244007 20140814 41644124400700001 BIB 7 15 4124400700002 REACTION (64-GD-154(N,G)64-GD-155,,SIG,,SPA) 4124400700003 INC-SPECT Reactor spectrum. 4124400700004 Thermal neutrons integral flux was monitored by 4124400700005 Li6 concentration change. 4124400700006 SAMPLE Natural Gd sample. Isotopic content, %: 4124400700007 Gd-154 - 1.98+-0.05, Gd-155 - 13.03+-0.13, 4124400700008 Gd-156 - 20.71+-0.11, Gd-157 - 15.53+-0.06, 4124400700009 Gd-158 - 24.84+-0.08. 4124400700010 ANALYSIS Calculated from measured reactor value using 4124400700011 saturated Gd-155/Gd-154 concentration ratio 4124400700012 MISC-COL (MISC) Concentrations ratio Gd155 to Gd154 4124400700013 STATUS (TABLE) Table 2 of AE,22,(2),133,1967. 4124400700014 HISTORY (19970428T) * * Converted from SUBENT 80373003 4124400700015 Energy corrected from 2.35E-8 to 2.53E-8 MEV * * 4124400700016 (19990406U) 'MXW' changed to 'SPA' in SF8 4124400700017 ENDBIB 15 0 4124400700018 NOCOMMON 0 0 4124400700019 DATA 5 1 4124400700020 EN-DUMMY DATA DATA-ERR MISC MISC-ERR 4124400700021 MEV B B NO-DIM NO-DIM 4124400700022 2.5300E-08 125. 32. 3.5E-3 0.9E-3 4124400700023 ENDDATA 3 0 4124400700024 ENDSUBENT 23 0 4124400799999 ENDENTRY 7 0 4124499999999