ENTRY 21686 20230316 231621686 0 1 SUBENT 21686001 20230316 231621686 1 1 BIB 12 43 21686 1 2 TITLE Nuclear charge distribution in fission: fractional 21686 1 3 cumulative yields of isotopes of krypton and xenon 21686 1 4 in reactions Cf-249(n-th,f) and Cf-250(s.f.) 21686 1 5 AUTHOR (H.-H.Meixler,K.Wolfsberg,H.O.Denschlag) 21686 1 6 INSTITUTE (2GERMNZ) Institut fuer Kernchemie, University of 21686 1 7 Mainz. 21686 1 8 REFERENCE (J,CJC,61,665,1983) Final publ. 21686 1 9 (P,MAINZ-1976,100,1977) - same results. 21686 1 10 (P,MAINZ-75,113,1976) - same results. 21686 1 11 (W,DENSCHLAG,19801006) Private communication of 21686 1 12 H.A.Denschlag with experimental details and data. 21686 1 13 (T,MEIXLER,1980) Ph.D. Thesis, Mainz. 21686 1 14 FACILITY (REAC,2GERMNZ) TRIGA-reactor. 21686 1 15 REL-REF (M,13097001,A.C.Wahl+,J,PR,126,1112,1962) For 21686 1 16 experimental method. 21686 1 17 METHOD (CHSEP) Radiochemical emanation method for fission 21686 1 18 rare gases. 21686 1 19 Rb and Xe were isolated radiochemically from the 21686 1 20 other fission products. 21686 1 21 DETECTOR (GELI) For gamma rays 21686 1 22 (PROPC) Anti-coincidence beta counter. 21686 1 23 ANALYSIS The number of fission noble gas atoms of a 21686 1 24 particular mass escaping from a stearate layer 21686 1 25 is compared to the total number of fission products 21686 1 26 of that particular chain. 21686 1 27 DECAY-DATA ((1.)36-KR-89,3.18MIN,B) 21686 1 28 ((2.)36-KR-91,8.6SEC,B) 21686 1 29 ((3.)36-KR-92,1.84SEC,B) 21686 1 30 ((4.)54-XE-139,39.7SEC,B) 21686 1 31 ((5.)54-XE-140,14.SEC,B) 21686 1 32 ((6.)54-XE-141,1.73SEC,B) 21686 1 33 ((7.)54-XE-142,1.2SEC,B) 21686 1 34 ((8.)54-XE-143,0.96SEC,B) 21686 1 35 STATUS (TABLE) Tbl. 1 and text from Can.J.Chem.61,665,1983 21686 1 36 Data from private communication of Denschlag. 21686 1 37 HISTORY (19801017C) G.C. 21686 1 38 (19801104E) 21686 1 39 (20121109A) SD: Updated to new date formats,lower case.21686 1 40 Corrected according last EXFOR rules and Dict. 21686 1 41 INC-SOURCE moved to Subent 2. BIB update. COMMON moved21686 1 42 to Subent 2 from Subent 1. Ref. on CJC and MAINZ-75 21686 1 43 were added. Subent 3 was added from 20711002. 21686 1 44 (20230316U) SD: Ref. MAINZ-1976 added. 21686 1 45 ENDBIB 43 0 21686 1 46 NOCOMMON 0 0 21686 1 47 ENDSUBENT 46 0 21686 199999 SUBENT 21686002 20121109 22342168600200001 BIB 4 10 2168600200002 REACTION ((98-CF-249(N,F)ELEM/MASS,CUM,FY,,MXW)/ 2168600200003 (98-CF-249(N,F)MASS,CHN,FY,,MXW)) 2168600200004 SAMPLE .The target consisted of 10 mu-g of 249Cf 2168600200005 electrodeposited on a platinum disc. In part of the 2168600200006 experiments (143Xe) a target of 10 mu-g of 249Cf 2168600200007 deposited on a steel cylinder was used 2168600200008 INC-SOURCE (REAC) .Thermal Maxwellian neutron spectrum 2168600200009 from reactor. Neutron flux of 3 x 10**10 n/cm2/sec 2168600200010 ERR-ANALYS (DATA-ERR) .Total error, including statistical and 2168600200011 systematic errors is given. 2168600200012 ENDBIB 10 0 2168600200013 COMMON 1 3 2168600200014 EN-DUMMY 2168600200015 EV 2168600200016 2.5300E-02 2168600200017 ENDCOMMON 3 0 2168600200018 DATA 6 8 2168600200019 ELEMENT MASS DATA +DATA-ERR -DATA-ERR DECAY-FLAG 2168600200020 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 2168600200021 36.0 89.0 0.776 0.010 0.010 1.02168600200022 36.0 91.0 0.320 0.031 0.017 2.02168600200023 36.0 92.0 0.095 0.013 0.013 3.02168600200024 54.0 139.0 0.320 0.035 0.035 4.02168600200025 54.0 140.0 0.125 0.020 0.020 5.02168600200026 54.0 141.0 0.040 0.003 0.003 6.02168600200027 54.0 142.0 0.009 0.003 0.003 7.02168600200028 54.0 143.0 0.0022 0.0008 0.0008 8.02168600200029 ENDDATA 10 0 2168600200030 ENDSUBENT 29 0 2168600299999 SUBENT 21686003 20121109 22342168600300001 BIB 3 9 2168600300002 REACTION ((98-CF-250(0,F)ELEM/MASS,CUM,FY)/ 2168600300003 (98-CF-250(0,F)MASS,CHN,FY)) 2168600300004 SAMPLE The target was 1.2 mu-g of 250Cf electrodeposited on a 2168600300005 platinum disc 2168600300006 ERR-ANALYS (DATA-ERR) .Total error, including statistical and 2168600300007 systematic errors is given. 2168600300008 Uncertainties mainly due to the poor counting 2168600300009 statistics obtained because of the rather weak 2168600300010 250Cf source. 2168600300011 ENDBIB 9 0 2168600300012 NOCOMMON 0 0 2168600300013 DATA 7 6 2168600300014 ELEMENT MASS DATA +DATA-ERR -DATA-ERR DATA-MAX 2168600300015 DECAY-FLAG 2168600300016 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 2168600300017 NO-DIM 2168600300018 36.0 91.0 0.348 0.043 0.032 2168600300019 2.0 2168600300020 36.0 92.0 0.099 0.042 0.021 2168600300021 3.0 2168600300022 54.0 139.0 0.236 0.060 0.060 2168600300023 4.0 2168600300024 54.0 140.0 0.147 0.070 0.070 2168600300025 5.0 2168600300026 54.0 141.0 0.091 0.104 0.067 2168600300027 6.0 2168600300028 54.0 142.0 3.6 2168600300029 7.0 2168600300030 ENDDATA 16 0 2168600300031 ENDSUBENT 30 0 2168600399999 SUBENT 21686004 20120708 22342168600400001 BIB 4 7 2168600400002 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 2168600400003 (92-U-235(N,F)MASS,CHN,FY,,MXW)) 2168600400004 fractional cumulative yields. 2168600400005 INC-SOURCE (REAC) Triga research reactor of Mainz (3. x 10**10 2168600400006 thermal neutrons per cm2 and sec.) 2168600400007 INC-SPECT Thermal Maxwellian flux for U-235 2168600400008 HISTORY (20120708T) SD: Subent was added from Entry 20711. 2168600400009 ENDBIB 7 0 2168600400010 COMMON 1 3 2168600400011 EN-DUMMY 2168600400012 EV 2168600400013 2.5300E-02 2168600400014 ENDCOMMON 3 0 2168600400015 DATA 4 2 2168600400016 ELEMENT MASS DATA DATA-ERR 2168600400017 NO-DIM NO-DIM NO-DIM NO-DIM 2168600400018 5.4000E+01 1.3900E+02 8.1000E-01 4.0000E-02 2168600400019 5.4000E+01 1.4000E+02 5.8000E-01 1.0000E-02 2168600400020 ENDDATA 4 0 2168600400021 ENDSUBENT 20 0 2168600499999 ENDENTRY 4 0 2168699999999