ENTRY 20879 20171022 22682087900000001 SUBENT 20879001 20171022 22682087900100001 BIB 13 54 2087900100002 INSTITUTE (2GERMNZ) Institut fuer Kernchemie. 2087900100003 REFERENCE (J,JIN,39,753,1977) 2087900100004 AUTHOR (W.Rudolph,K.-L.Kratz,G.Herrmann) 2087900100005 TITLE Half-lives, fission yields and neutron emission 2087900100006 probabilities of neutron-rich antimony isotopes 2087900100007 FACILITY (REAC,2GERMNZ) Mainz Triga reactor. 2087900100008 INC-SOURCE (REAC) Neutron pulses of 30 millisec FWHM, 2087900100009 integrated flux of 10**4 n/cm2. 2087900100010 INC-SPECT Thermal flux. 2087900100011 SAMPLE 0.1mg 235-U plus a known activity of 60d 124-Sb, 2087900100012 dissolved in 0.1ml of 0.1 M H-Cl, containing some S-O22087900100013 METHOD (ACTIV) 2087900100014 (CHSEP) fast system, see JIN. Counting of antimony 2087900100015 sample was started after 2.7 sec chemical separation 2087900100016 DETECTOR (FISCH) As flux monitor. 2087900100017 (PROPC) 8 He-3 counters with an efficiency of 2087900100018 12.0 +-0.4 % (Am-Li reference ), for neutrons . 2087900100019 (GELI) diode with a resolution of 2.3keV FWHM at 2087900100020 1332keV and an efficiency of 18% of an Na-I 2087900100021 3 by 3 in. crystal. 2087900100022 PART-DET (N) 2087900100023 (G) 2087900100024 ADD-RES . Table 4 of J.Inorg.Nucl.Chem.,39,753,1977 2087900100025 Zp calculated from measured yield data and previously 2087900100026 known data for chains 134 and 135 from a 2087900100027 compilation of Woell and Denschlag (priv.comm): 2087900100028 Mass Zpropable SIGMA-value 2087900100029 134. 52.078 +- 0.032 0.500 +- 0.001 2087900100030 135. 52.546 +- 0.013 0.531 +- 0.001 2087900100031 SIGMA-value of the mass-chains distribution , 2087900100032 Zp errors include uncertainties due to: 2087900100033 * amount of U-235, 2087900100034 * chemical yield, 2087900100035 * counting geometry, 2087900100036 * fission yields of iodine reference, 2087900100037 * scatter in fractional yield. 2087900100038 From these data fractional independent yield of 2087900100039 Te-134 was calculated to be 82 % . 2087900100040 HISTORY (19790410C) WWO. 2087900100041 (19800723A) Changes in Subents. 2087900100042 (19821119A) Subent 5 deleted, delayed neutron emission 2087900100043 data not coded in EXFOR. 2087900100044 (19830202A) A.P.T. Subent 002 deleted in error. It is 2087900100045 now reinstated as Subent 007. Subent 005 deleted. 2087900100046 (20151212A) SD:Updated to new date formats,lower case. 2087900100047 DECAY-DATA corrected in Subents 006,007. ERR-ANALYS 2087900100048 moved to Subents 006,007. MONITOR moved to Subent 004. 2087900100049 (20171022A) M.M. COMMENT was added. 2087900100050 Subents 008-011 were added (Pn, Table 5). 2087900100051 EN-DUMMY was moved in Subents 004-007. 2087900100052 NOSUBENT lines were inserted for Subents 002, 005 , 2087900100053 Subent 003 was restored, 2087900100054 Subents 004,006 data were moved in ADD-RES, 2087900100055 according to comments of N.Otsuka(NDS,IAEA) 2087900100056 ENDBIB 54 0 2087900100057 NOCOMMON 0 0 2087900100058 ENDSUBENT 57 0 2087900199999 NOSUBENT 20879002 20171022 22682087900200001 SUBENT 20879003 20171022 22682087900300001 BIB 8 18 2087900300002 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 2087900300003 (92-U-235(N,F)MASS,CHN,FY)) 2087900300004 RESULT (FRCUM) 2087900300005 DECAY-DATA ((0.)51-SB-134-G,0.8SEC) 2087900300006 ((1.)51-SB-134-M,10.SEC) 2087900300007 ANALYSIS Sb-134-G yield was derived from that of Sb-134-M 2087900300008 using isomeric ratio of Kerek+. 2087900300009 REL-REF (R,,A.Kerek+,J,NP/A,195,177,1972) 2087900300010 CORRECTION .For - 2087900300011 contamination in irradiated sample, e.t.c. 2087900300012 STATUS (TABLE) Table 3 of J.Inorg.Nucl.Chem.,39,753,1977. 2087900300013 (SPSDD,20878004) Superseded by newer publication. 2087900300014 HISTORY (19790410C) WWO. 2087900300015 (19790518E) 2087900300016 (19800723D) Deleted, duplicate data with 20878.004 2087900300017 (19800808D) 2087900300018 (19800723S) Subent was restored from archive, data 2087900300019 were added from Table 3. 2087900300020 ENDBIB 18 0 2087900300021 COMMON 2 3 2087900300022 EN-DUMMY ELEMENT 2087900300023 EV NO-DIM 2087900300024 0.0253 51. 2087900300025 ENDCOMMON 3 0 2087900300026 DATA 5 4 2087900300027 MASS ISOMER DATA DATA-ERR DECAY-FLAG 2087900300028 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 2087900300029 134. 1. 6.2 E-02 0.4 E-02 1. 2087900300030 134. 0. 1.32E-02 0.08E-02 0. 2087900300031 134. 7.4 E-02 0.4 E-02 2087900300032 135. 2.3 E-02 0.1 E-02 2087900300033 ENDDATA 6 0 2087900300034 ENDSUBENT 33 0 2087900399999 NOSUBENT 20879004 20171022 22682087900400001 NOSUBENT 20879005 20171022 22682087900500001 NOSUBENT 20879006 20171022 22682087900600001 SUBENT 20879007 20171022 22682087900700001 BIB 9 46 2087900700002 REACTION (92-U-235(N,F)ELEM/MASS,DL/CUM,NU,,MXW) 2087900700003 Delayed NU from specific precursors. 2087900700004 REL-REF (A,23349002,L.Tomlinson+,J,JIN,30,1649,1968) 2087900700005 MONITOR (92-U-235(N,F),DL/GRP,NU,,MXW) 2087900700006 DECAY-DATA (51-SB-134-M,10.0SEC,DN) Delayed neutrons. 2087900700007 (51-SB-135,1.706SEC,DN) 2087900700008 (51-SB-136,0.75SEC,DN) 2087900700009 Half-life value measured. 2087900700010 ANALYSIS (DECAY) Neutron decay curve analyzed. 2087900700011 Data were converted into absolute neutron yields by 2087900700012 relating them to the absolute neutron group abundances 2087900700013 of U-235, which are well known (see G.R.Keepin, 2087900700014 Physics of Nuclear Kinetic, Add.Wesley,NY (1965)). The 2087900700015 neutron-decay curve of 32 unseparated samples of 2087900700016 irradiated 235U (0.01 mg) was analyzed in terms of the 2087900700017 six neutron groups characterized by periods of 55,22,6,2087900700018 2,0.6 and 0.2 sec. From the initial activities of these2087900700019 periods follows a calibration of the neutron counter in2087900700020 terms of absolute neutron abundances 2087900700021 (neutrons/10**4/fissions). 2087900700022 CORRECTION For - 2087900700023 contamination in the irradiated sample, as 2087900700024 0.2% arsenic, 0.03% selenium, 0.02% tellurium, 2087900700025 8*10-3% bromine and iodine, and noble gases 2087900700026 less than 0.1%, 2087900700027 further for - 2087900700028 background as being 3 counts/min., 2087900700029 The amount of 235-U, 2087900700030 the neutron flux, 2087900700031 the chemical yield, 2087900700032 counting geometry. 2087900700033 ERR-ANALYS (DATA-ERR) The errors given include all 2087900700034 uncertainties due to: 2087900700035 * amount of U-235, 2087900700036 * chemical yield, 2087900700037 * counting geometry, 2087900700038 * fission yields of iodine reference, 2087900700039 * scatter in fractional yield. 2087900700040 STATUS (TABLE) Table 2 from J.Inorg.Nucl.Chem.,39,753,1977. 2087900700041 HISTORY (19800723A) Reaction re-defined, data factor removed. 2087900700042 (19830202A) A.P.T. This Subent was originally numbered 2087900700043 002. It was deleted in error and is now reinstated. 2087900700044 (20151212A) SD: Col. ISOMER was added to DATA section. 2087900700045 Sb-134 -> Sb-134 in DECAY-DATA (half-life=10.sec).Units2087900700046 NO-DIM -> PRT/FIS at DATA and DATA-ERR cols. BIB update2087900700047 (20171022A) M.M. CUM was added in SF5 2087900700048 ENDBIB 46 0 2087900700049 COMMON 1 3 2087900700050 EN-DUMMY 2087900700051 EV 2087900700052 2.5000E-02 2087900700053 ENDCOMMON 3 0 2087900700054 DATA 5 3 2087900700055 ELEMENT MASS ISOMER DATA DATA-ERR 2087900700056 NO-DIM NO-DIM NO-DIM PRT/FIS PRT/FIS 2087900700057 51. 134. 1. 0.043E-04 0.006E-04 2087900700058 51. 135. 3.1E-04 0.3E-04 2087900700059 51. 136. 0.7E-04 0.3E-04 2087900700060 ENDDATA 5 0 2087900700061 ENDSUBENT 60 0 2087900799999 SUBENT 20879008 20171022 22682087900800001 BIB 7 16 2087900800002 REACTION (51-SB-134-M(0,B-)52-TE-134,,PN,,,DERIV) 2087900800003 DECAY-DATA (51-SB-134-M,10.5SEC) 10.5+-0.6 sec from neutron decay,2087900800004 10.43+-0.14 sec from gamma decay. 2087900800005 (52-TE-134,,DG,211.,,DG,79.,,DG,767.) 2087900800006 ANALYSIS Neutron emission probability Pn is ratio of 2087900800007 absolute neutron abundances ( Subent 007) to the 2087900800008 respective cumulative fission yields, which were 2087900800009 obtained by multiplying exp.mass yields of Walker with 2087900800010 the fractional cumulative fis.yield ( Subent 003). 2087900800011 REL-REF (D,,W.H.Walker,R,AECL-4704,1974) 2087900800012 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 2087900800013 article 2087900800014 STATUS (TABLE) Table 5 of J.Inorg.Nucl.Chem.,39,753,1977. 2087900800015 (DEP,20879007) Neutron abundances. 2087900800016 (DEP,20879003) Fractional cumulative fis. yield 2087900800017 HISTORY (20171022C) M.M. 2087900800018 ENDBIB 16 0 2087900800019 COMMON 1 3 2087900800020 EN-NRM 2087900800021 EV 2087900800022 0.0253 2087900800023 ENDCOMMON 3 0 2087900800024 DATA 2 1 2087900800025 DATA DATA-ERR 2087900800026 NO-DIM NO-DIM 2087900800027 0.00090 0.00015 2087900800028 ENDDATA 3 0 2087900800029 ENDSUBENT 28 0 2087900899999 SUBENT 20879009 20171022 22682087900900001 BIB 7 16 2087900900002 REACTION (51-SB-135(0,B-)52-TE-135,,PN,,,DERIV) 2087900900003 DECAY-DATA (51-SB-135,1.706SEC) 1.706+-0.014 sec from neutron 2087900900004 decay, 1.9+-0.2 from gamma-decay. 2087900900005 (52-TE-135,,DG,870.,0.253,DG,267.,0.119,DG,603.,1.0) 2087900900006 ANALYSIS Neutron emission probability Pn is ratio of 2087900900007 absolute neutron abundances ( Subent 007) to the 2087900900008 respective cumulative fission yields, which were 2087900900009 obtained by multiplying exp.mass yields of Walker with 2087900900010 the fractional cumulative fis.yield (Subent 003) 2087900900011 REL-REF (D,,W.H.Walker,R,AECL-4704,1974) 2087900900012 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 2087900900013 article 2087900900014 STATUS (TABLE) Table 5 of J.Inorg.Nucl.Chem.,39,753,1977. 2087900900015 (DEP,20879007) Neutron abundances. 2087900900016 (DEP,20879003) Fractional cumulative fis. yield 2087900900017 HISTORY (20171022C) M.M. 2087900900018 ENDBIB 16 0 2087900900019 COMMON 1 3 2087900900020 EN-NRM 2087900900021 EV 2087900900022 0.0253 2087900900023 ENDCOMMON 3 0 2087900900024 DATA 2 1 2087900900025 DATA DATA-ERR 2087900900026 NO-DIM NO-DIM 2087900900027 0.199 0.021 2087900900028 ENDDATA 3 0 2087900900029 ENDSUBENT 28 0 2087900999999 SUBENT 20879010 20171022 22682087901000001 BIB 8 17 2087901000002 REACTION (51-SB-136(0,B-)52-TE-136,,PN,,,DERIV) 2087901000003 DECAY-DATA (51-SB-136,0.75SEC) 0.75+-0.20 sec from neutron decay 2087901000004 (52-TE-136,17.5SEC,DG,331.) 2087901000005 ANALYSIS Neutron emission probability Pn is ratio of 2087901000006 absolute neutron abundances ( Subent 007) to the 2087901000007 respective cumulative fission yields, which were 2087901000008 obtained by multiplying exp.mass yields of Walker with 2087901000009 the estimated fractional cumulative fis.yield 0.36 % 2087901000010 ASSUMED (ASSUM,(92-U-235(N,F)51-SB-136,CUM,FY,,MXW)/ 2087901000011 (92-U-235(N,F)MASS,CHN,FY)) 2087901000012 REL-REF (D,,W.H.Walker,R,AECL-4704,1974) 2087901000013 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 2087901000014 article 2087901000015 STATUS (TABLE) Table 5 of J.Inorg.Nucl.Chem.,39,753,1977. 2087901000016 (DEP,20879007) Neutron abundances. 2087901000017 (DEP,20879003) Fractional cumulative fis. yield 2087901000018 HISTORY (20171022C) M.M. 2087901000019 ENDBIB 17 0 2087901000020 COMMON 1 3 2087901000021 EN-NRM 2087901000022 EV 2087901000023 0.0253 2087901000024 ENDCOMMON 3 0 2087901000025 DATA 3 1 2087901000026 DATA DATA-ERR ASSUM 2087901000027 NO-DIM NO-DIM NO-DIM 2087901000028 0.32 0.14 0.0036 2087901000029 ENDDATA 3 0 2087901000030 ENDSUBENT 29 0 2087901099999 SUBENT 20879011 20171022 22682087901100001 BIB 6 10 2087901100002 REACTION (52-TE-136(0,B-)53-I-136,,PN,,,DERIV) 2087901100003 DECAY-DATA (52-TE-136,25.SEC) 25.+-5. sec from neutron decay, 2087901100004 ~15.sec from gamma-decay 2087901100005 ANALYSIS Neutron emission probability was derived from 2087901100006 neutron intensity ratio of Sb-136 and Te-136. 2087901100007 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 2087901100008 article 2087901100009 STATUS (TABLE) Table 5 of J.Inorg.Nucl.Chem.,39,753,1977. 2087901100010 (DEP,20879010) Sb-136 neutron emission probability. 2087901100011 HISTORY (20171022C) M.M. 2087901100012 ENDBIB 10 0 2087901100013 NOCOMMON 0 0 2087901100014 DATA 2 1 2087901100015 DATA DATA-ERR 2087901100016 NO-DIM NO-DIM 2087901100017 0.007 0.004 2087901100018 ENDDATA 3 0 2087901100019 ENDSUBENT 18 0 2087901199999 ENDENTRY 11 0 2087999999999