ENTRY 21530 20090315 22082153000000001 SUBENT 21530001 20090315 22082153000100001 BIB 13 31 2153000100002 INSTITUTE (2BLGMOL) C.E.N./S.C.K. Mol. 2153000100003 REFERENCE (J,ZP/A,275,359,197512) 2153000100004 AUTHOR (P.Fettweis,P.Del Marmol) 2153000100005 TITLE -Study of short lived Ru isotopes produced in thermal 2153000100006 neutron fission of U-235 -. 2153000100007 FACILITY (REAC ) BR-1 graphite reactor. 2153000100008 INC-SOURCE (REAC ) Thermal graphite reactor. 2153000100009 INC-SPECT .Thermal maxwellian spectrum. 2153000100010 SAMPLE .Aqueous solution containing 250mg U-235 as uranyl 2153000100011 nitrate and ruthenium tracer irradiated. Ru fission 2153000100012 products seperated by oxidation to volatile RuO4 2153000100013 by Cl gas. Irradiation times of 5 to 250 secs, with 2153000100014 gamma counting starting 10 secs after irradiation. 2153000100015 DETECTOR (GELI ) Ge(Li) detector for gamma counting of 2153000100016 seperated Ru isotopes. 2153000100017 COMMENT .Gamma decay lines are assigned to various Ru 2153000100018 isotopes from a=107 to 110, or to their daughter 2153000100019 products on the basis of half lives, intensity 2153000100020 ratios and known level properties. Ru-111 is 2153000100021 identified with a half-life of 1.5+-0.3 secs. 2153000100022 STATUS .Table 6, fission yields. 2153000100023 HISTORY (19800429C) 2153000100024 (19800603E) 2153000100025 (20090315U) Last checking has been done. 2153000100026 ERR-ANALYS .Uncertainties are one standard deviation, primarilly 2153000100027 statistical from the set of measurements combined 2153000100028 with unceratinties in absolute gamma intensities, 2153000100029 discrepancies in decay parameters such as 2153000100030 half-lives, unknown isomeric states and inter- 2153000100031 correlation of results could lead to much larger 2153000100032 errors. 2153000100033 ENDBIB 31 0 2153000100034 COMMON 1 3 2153000100035 EN-DUMMY 2153000100036 EV 2153000100037 2.53E-02 2153000100038 ENDCOMMON 3 0 2153000100039 ENDSUBENT 38 0 2153000199999 SUBENT 21530002 20090315 22082153000200001 BIB 5 21 2153000200002 REACTION (92-U-235(N,F)ELEM/MASS,IND,FY,,MXW) 2153000200003 Independent fission yields. 2153000200004 DECAY-DATA (44-RU-103,,DG,497.,0.87) 2153000200005 (44-RU-105,,DG,724.,0.49) 2153000200006 (44-RU-107,4.2MIN,DG,195.,0.116) 2153000200007 (44-RU-108,4.5MIN,DG,165.,0.32) 2153000200008 (44-RU-109,34.5SEC,DG,359.,0.18) 2153000200009 (44-RU-111,1.5SEC,B-) Beta counting of Pd-111 relative 2153000200010 to Pd-109. 2153000200011 MONITOR (92-U-235(N,F)44-RU-105,IND,FY,,MXW) 2153000200012 Value taken from meek and rider as 0.99 pc/fis. 2153000200013 More precisely, the 105 cumulative mass yield 2153000200014 used in this measurement was that of Tc-105 2153000200015 as the irradiations are too short to show any 2153000200016 contribution from 4.4hr Ru-105.. To this an 2153000200017 independant fission yield contribution of 1 pc 2153000200018 for Ru-105 was added. 2153000200019 STATUS .Table 6. 2153000200020 HISTORY (19800429C) 2153000200021 (19800603E) 2153000200022 (20090315U) Last checking has been done. 2153000200023 ENDBIB 21 0 2153000200024 COMMON 1 3 2153000200025 MONIT 2153000200026 PC/FIS 2153000200027 9.9E-01 2153000200028 ENDCOMMON 3 0 2153000200029 DATA 4 5 2153000200030 ELEMENT MASS DATA DATA-ERR 2153000200031 NO-DIM NO-DIM PC/FIS PC/FIS 2153000200032 4.4E+01 1.03E+02 3.43 1.1E-01 2153000200033 4.4E+01 1.07E+02 1.3E-01 1.E-02 2153000200034 4.4E+01 1.08E+02 4.2E-02 2.E-03 2153000200035 4.4E+01 1.09E+02 2.7E-02 3.E-03 2153000200036 4.4E+01 1.11E+02 1.7E-02 6.E-03 2153000200037 ENDDATA 7 0 2153000200038 ENDSUBENT 37 0 2153000299999 ENDENTRY 2 0 2153099999999