ENTRY 23709 20200520 228823709 0 1 SUBENT 23709001 20200505 228823709 1 1 BIB 17 44 23709 1 2 TITLE Independent yields of 124Sb and 126Sb in thermal 23709 1 3 neutron induced fission and their implication on the 23709 1 4 empirical Zp function 23709 1 5 AUTHOR (P.O.Strom,G.R.Grant,A.C.Pappas) 23709 1 6 REFERENCE (J,CJC,43,2493,1965) 23709 1 7 INSTITUTE (2NOROSL) 23709 1 8 FACILITY (REAC,2DENRIS) DR-2 reactor of Danish Atomic Energy 23709 1 9 Commission, Riso. 23709 1 10 INC-SOURCE (THCOL) 23709 1 11 INC-SPECT Thermal neutrons. Flux ~2.E+12 n/(cm2*sec) was constan23709 1 12 within +-10% . Cd ratio ~50. 23709 1 13 SAMPLE 1. Natural U as UO(3), 800 mg , 0.72 % U-235. 23709 1 14 2. U enriched in U-235 to 19.9% as UO(3), 25 mg 23709 1 15 3.&4. U enriched in U-235 to 93.3% as U(2)O(8), ~10 mg23709 1 16 And blank sample - quartz ampule. 23709 1 17 DETECTOR (PROPC) Methane flow beta-proportional counter. 23709 1 18 (NAICR) Intertechnique 400-channel gamma-pulse height 23709 1 19 analyzer with 2.5 inch x 3 inch Harshaw 23709 1 20 thallium-activated sodium iodine crystal. 23709 1 21 METHOD (CHSEP) 1-2 week irradiation. ~1 month cooling before 23709 1 22 radiochemical separation. 23709 1 23 Chemical yields were determined by weighting. 23709 1 24 MONITOR (92-U-235(N,F)56-BA-140,IND,FY) 23709 1 25 DECAY-MON (56-BA-140,12.80D) 23709 1 26 MONIT-REF (,J.W.Barnes,R,LA-1721,1958) 2nd edition. 23709 1 27 REL-REF (N,,B.J.Dropesky+,J,BAP,8,377,1963) 23709 1 28 Decay scheme for Sb-126 23709 1 29 (N,,J.Vanhorenbeeck,J,NP,37,90,1962) 23709 1 30 Decay scheme for Sb-127 23709 1 31 ERR-ANALYS (ERR-1) Error in determination of the number of 23709 1 32 fissions. 23709 1 33 (ERR-2) Counting efficiency error 23709 1 34 CORRECTION . For contributions from reactions: 23709 1 35 Sb-124-g(N,G)Sb-125 - negligible. 23709 1 36 Sb-123(N,G)Sb-124-g - ~0.2%. 23709 1 37 Te-124(N,P)Sb-124 and I-127(N,A)Sb-124 - no influence 23709 1 38 on results. 23709 1 39 For Sb-124-g atoms produced in ampoules - ~2%. 23709 1 40 Total corrections 2-3 % for Sb-124. 23709 1 41 . For background due to 2.7 yr Sb-125 and 23709 1 42 60 day Sb-124-g. 23709 1 43 For contribution of Te-126(N,P)Sb-126 reaction - 23709 1 44 negligible. 23709 1 45 HISTORY (20200520C) M.M. 23709 1 46 ENDBIB 44 0 23709 1 47 COMMON 4 3 23709 1 48 EN-DUMMY MONIT ERR-1 ERR-2 23709 1 49 EV PC/FIS PER-CENT PER-CENT 23709 1 50 0.0253 6.35 10. 10. 23709 1 51 ENDCOMMON 3 0 23709 1 52 ENDSUBENT 51 0 23709 199999 SUBENT 23709002 20200520 228823709 2 1 BIB 6 25 23709 2 2 REACTION (92-U-235(N,F)ELEM/MASS,IND,FY) 23709 2 3 Apparent independent fission yields, units are % . 23709 2 4 Includes part of the higher isomeric states. 23709 2 5 DECAY-DATA (51-SB-127,3.9D) 23709 2 6 (52-TE-127-G,93.HR) This state HL=93.hr is given in 23709 2 7 the article, but most probably there is a misprint: 23709 2 8 93.hr -> 9.3 hr ( 9.35hr is in Nuclear Walllet Cards 23709 2 9 of J.K.Tuli,2011) 23709 2 10 (52-TE-127-M,105.D) 23709 2 11 (51-SB-126-G,12.5D,B-) 23709 2 12 (51-SB-125,2.7YR) 23709 2 13 (52-TE-125-M,58.D) 23709 2 14 (51-SB-124-G,60.D,DG,1690.) 23709 2 15 FLAG (1.) Sample 1 23709 2 16 (2.) Sample 2 23709 2 17 (3.) Sample 3 23709 2 18 (4.) Sample 4 23709 2 19 (5.) Average. for Sb-124 - only for samples 3 and 4. 23709 2 20 REL-REF (A,,G.Lange+,W,HERRMANN,1964) 23709 2 21 Personal communication from G.Herrmann and G.Lange. 23709 2 22 (0.90+-0.25)*10**-3 % for Sb-126-G. 23709 2 23 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 23709 2 24 article. 23709 2 25 STATUS (TABLE) Table II of 23709 2 26 Canadian Journal of Chemistry,v.43,p.2493,1965 23709 2 27 ENDBIB 25 0 23709 2 28 COMMON 2 3 23709 2 29 ELEMENT ISOMER 23709 2 30 NO-DIM NO-DIM 23709 2 31 51. 0. 23709 2 32 ENDCOMMON 3 0 23709 2 33 DATA 4 10 23709 2 34 MASS DATA DATA-ERR FLAG 23709 2 35 NO-DIM PC/FIS PC/FIS NO-DIM 23709 2 36 124. 1.35 E-04 1. 23709 2 37 124. 0.55 E-04 2. 23709 2 38 124. 9.3 E-06 3. 23709 2 39 124. 9.6 E-06 4. 23709 2 40 124. 9.5 E-06 1.4 E-06 5. 23709 2 41 126. 0.91 E-03 1. 23709 2 42 126. 0.88 E-03 2. 23709 2 43 126. 1.11 E-03 3. 23709 2 44 126. 1.23 E-03 4. 23709 2 45 126. 1.04 E-03 0.18 E-03 5. 23709 2 46 ENDDATA 12 0 23709 2 47 ENDSUBENT 46 0 23709 299999 SUBENT 23709003 20200520 228823709 3 1 BIB 6 14 23709 3 2 REACTION 1(92-U-235(N,F)ELEM/MASS,IND,FY,,,DERIV) 23709 3 3 2(92-U-235(N,F)ELEM/MASS,IND,FY,,FRC,DERIV) 23709 3 4 ANALYSIS 1 Total independent fission yield was derived from 23709 3 5 measured independent yield for ground state. 23709 3 6 2 Fractional independent yield was derived from total 23709 3 7 idependent yield and chain yield (see ASSUM) 23709 3 8 ASSUMED 2(ASSUM,92-U-235(N,F)MASS,CHN,FY) 23709 3 9 REL-REF (R,,S.Katcoff,J,NUC,18,(11),201,1960) ASSUM values 23709 3 10 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 23709 3 11 article. 23709 3 12 STATUS (TABLE) Table V of 23709 3 13 Canadian Journal of Chemistry,v.43,p.2493,1965 23709 3 14 1(DEP,23709002) Measured independent yields for 23709 3 15 ground state. 23709 3 16 ENDBIB 14 0 23709 3 17 COMMON 1 3 23709 3 18 ELEMENT 23709 3 19 NO-DIM 23709 3 20 51. 23709 3 21 ENDCOMMON 3 0 23709 3 22 DATA 6 2 23709 3 23 MASS DATA 1DATA-ERR 1DATA 2DATA-ERR 2ASSUM 223709 3 24 NO-DIM PC/FIS PC/FIS NO-DIM NO-DIM PC/FIS 23709 3 25 124. 1.16 E-05 0.17 E-05 6.8 E-04 1.0 E-04 1.7 E-0223709 3 26 126. 3.72 E-03 0.61 E-03 3.7 E-02 0.6 E-02 0.10 23709 3 27 ENDDATA 4 0 23709 3 28 ENDSUBENT 27 0 23709 399999 SUBENT 23709004 20200520 228823709 4 1 BIB 5 10 23709 4 2 REACTION (92-U-235(N,F)MASS,(SEC),ZP,,,DERIV) 23709 4 3 ANALYSIS Empirical charge distribution was assumed as Gaussian,23709 4 4 see formula (1) in J,CJC,43,2493,1965 . 23709 4 5 REL-REF (N,,A.C.Wahl+,J,PR,126,1112,1962) 23709 4 6 ERR-ANALYS (DATA-ERR) Includes uncertainty in empirical constant 23709 4 7 of formula (1) and error of independent yields. 23709 4 8 STATUS (TABLE) Text page 2502 of 23709 4 9 Canadian Journal of Chemistry,v.43,p.2493,1965 23709 4 10 (DEP,23709002) Measured independent yields for 23709 4 11 ground state. 23709 4 12 ENDBIB 10 0 23709 4 13 NOCOMMON 0 0 23709 4 14 DATA 3 2 23709 4 15 MASS DATA DATA-ERR 23709 4 16 NO-DIM NO-DIM NO-DIM 23709 4 17 124. 48.49 0.20 23709 4 18 126. 49.39 0.14 23709 4 19 ENDDATA 4 0 23709 4 20 ENDSUBENT 19 0 23709 499999 ENDENTRY 4 0 2370999999999