ENTRY 33007 20211117 32033300700000001 SUBENT 33007001 20211117 32033300700100001 BIB 16 65 3300700100002 TITLE Charge distribution in the thermal neutron induced 3300700100003 fission of 229-Th 3300700100004 AUTHOR (S.S.Rattan,A.V.R.Reddy,R.J.Singh,Satya Prakash, 3300700100005 M.V.Ramaniah) 3300700100006 Old name = S.S.Rattan, New name = Sarbjit Singh 3300700100007 INSTITUTE (3INDTRM) 3300700100008 REFERENCE (J,RCA,33,189,1983) 3300700100009 (C,80WALTAI,,155,1980) preliminary data in table. 3300700100010 FACILITY (REAC,3INDTRM) Cirus reactor 3300700100011 INC-SPECT Thermal neutron flux of ~5.0E12 n/cm2-sec 3300700100012 SAMPLE Targets of 229-Th (~30 micro gram) were prepared on 3300700100013 platinum backing by electro deposition using 3300700100014 isopropyl alcohol 3300700100015 METHOD (REC) The fission fragments were collected by the 3300700100016 thin target-recoil-catcher technique. 3300700100017 (GSPEC) The decay of the fission products were 3300700100018 followed as a function of time using 3300700100019 gamma ray spectrometry 3300700100020 (EXTB)Thermal neutron from Cirus reactor were used 3300700100021 (RELFY) The growth and decay of the daughter product 3300700100022 related with the fractional cumulative yield (FCY) of 3300700100023 the parent and fractional independent yield (FIY) of 3300700100024 the daughter product with suitable equations as 3300700100025 described in the paper. 3300700100026 DETECTOR (GELI) 60 cm3 Ge(Li) detector Resolution 2.6 keV at 3300700100027 1332 keV 3300700100028 ANALYSIS (DECAY) The deacy of each daughter product in a given 3300700100029 mass chain was followed for suitable length of time. 3300700100030 CORRECTION The correction for the decay and growth during the 3300700100031 irradiation for the parent and daughter product 3300700100032 were incorporated in the equations 3300700100033 The errors due detector efficiency, self absorption 3300700100034 and scattering were getting cancelled as the samples 3300700100035 were counted in similar geometry. 3300700100036 The corrections for the loss of 135-Xe due to its high 3300700100037 absorption cross section were applied during 3300700100038 irradiation 3300700100039 DECAY-DATA Taken from chart of nuclides prepared by 3300700100040 Seelmann-Eggebert W., Pfenning, G., and Munzel, H. 3300700100041 Institute for Radiochemie, 3300700100042 Kernforschungszentrum, Karlsruhe, 1974. 3300700100043 STATUS (TABLE) Data is taken from table 1 and 2 of this paper 3300700100044 (Ref. Journal RCA,33,189,1983) 3300700100045 ERR-ANALYS (DATA-ERR) The errors listed are the standard 3300700100046 deviations between the results from five different 3300700100047 irradiations and various gamma rays. 3300700100048 Errors are statistical, given as 1 standard deviation. 3300700100049 COMMENT The FCY values for 135-I published in 3300700100050 Phy.Rev. C17, 188 (1978) for 252Cf(s,f) and in 3300700100051 Phy.Rev. C21, 1411(1980) for 245Cm(n,f) have been 3300700100052 corrected in this paper. 3300700100053 This comment is mentioned in this paper 3300700100054 (J,RCA,33,189,1983) on page 192. 3300700100055 Though this data have been coded in EXFOR under entry 3300700100056 number 30516001. The modified values are being given 3300700100057 in this entry. 3300700100058 HISTORY (20071003C) 3300700100059 (20080826A) SD,NO. Moved COMMON from Subent 001, 3300700100060 Energy changed from MeV to eV and 3300700100061 in Subents 002,003,005 added SPA in reaction code. 3300700100062 (20211025A) VS. 3300700100063 Reference: Nucl.Chem.and Radiochem.Symp., Waltair, 3300700100064 India 1980, p. 155 added. EN->EN-DUMMY. 3300700100065 Reaction code corrected and ERR-T -> DATA-ERR in 3300700100066 002-005. 3300700100067 ENDBIB 65 0 3300700100068 NOCOMMON 0 0 3300700100069 ENDSUBENT 68 0 3300700199999 SUBENT 33007002 20211117 32033300700200001 BIB 3 5 3300700200002 REACTION (90-TH-229(N,F)53-I-135,CUM,FY,,FRC/MXW) 3300700200003 DECAY-DATA (53-I-135,6.61HR,DG,1260.409,0.289) 3300700200004 (54-XE-135-G,9.10HR,DG,249.794,0.902) 3300700200005 HISTORY (20211025A) VS. REACTION ratio -> SF8=FRC 3300700200006 and SF8 SPA -> MXW. ERR-T -> DATA-ERR 3300700200007 ENDBIB 5 0 3300700200008 COMMON 1 3 3300700200009 EN 3300700200010 EV 3300700200011 0.0253 3300700200012 ENDCOMMON 3 0 3300700200013 DATA 2 1 3300700200014 DATA DATA-ERR 3300700200015 NO-DIM NO-DIM 3300700200016 0.950 0.015 3300700200017 ENDDATA 3 0 3300700200018 ENDSUBENT 17 0 3300700299999 SUBENT 33007003 20211117 32033300700300001 BIB 3 5 3300700300002 REACTION (90-TH-229(N,F)56-BA-140,CUM,FY,,FRC/MXW) 3300700300003 DECAY-DATA (56-BA-140,12.75D,DG,537.311,0.2439) 3300700300004 (57-LA-140,40.272HR,DG,487.021,0.443) 3300700300005 HISTORY (20211025A) VS. REACTION ratio -> SF8=FRC 3300700300006 and SF8 SPA -> MXW. ERR-T -> DATA-ERR 3300700300007 ENDBIB 5 0 3300700300008 COMMON 1 3 3300700300009 EN 3300700300010 EV 3300700300011 0.0253 3300700300012 ENDCOMMON 3 0 3300700300013 DATA 2 1 3300700300014 DATA DATA-ERR 3300700300015 NO-DIM NO-DIM 3300700300016 0.926 0.019 3300700300017 ENDDATA 3 0 3300700300018 ENDSUBENT 17 0 3300700399999 SUBENT 33007004 20211117 32033300700400001 BIB 4 6 3300700400002 REACTION (98-CF-252(0,F)53-I-135,CUM,FY,,FRC/MXW) 3300700400003 DECAY-DATA (53-I-135,6.61HR,DG,1260.409,0.289) 3300700400004 (54-XE-135-G,9.10HR,DG,249.794,0.902) 3300700400005 COMMENT Data mentioned in this paper on page 192 3300700400006 HISTORY (20211025A) VS. REACTION ratio -> SF8=FRC 3300700400007 ERR-T -> DATA-ERR 3300700400008 ENDBIB 6 0 3300700400009 NOCOMMON 0 0 3300700400010 DATA 2 1 3300700400011 DATA DATA-ERR 3300700400012 NO-DIM NO-DIM 3300700400013 0.950 0.01 3300700400014 ENDDATA 3 0 3300700400015 ENDSUBENT 14 0 3300700499999 SUBENT 33007005 20211117 32033300700500001 BIB 4 6 3300700500002 REACTION (96-CM-245(N,F)53-I-135,CUM,FY,,FRC/MXW) 3300700500003 DECAY-DATA (53-I-135,6.61HR,DG,1260.409,0.289) 3300700500004 (54-XE-135-G,9.10HR,DG,249.794,0.902) 3300700500005 COMMENT Data mentioned in this paper on page 192 3300700500006 HISTORY (20211025A) VS. REACTION ratio -> SF8=FRC 3300700500007 and SF8 SPA -> MXW. ERR-T -> DATA-ERR 3300700500008 ENDBIB 6 0 3300700500009 COMMON 1 3 3300700500010 EN-DUMMY 3300700500011 EV 3300700500012 0.0253 3300700500013 ENDCOMMON 3 0 3300700500014 DATA 2 1 3300700500015 DATA DATA-ERR 3300700500016 NO-DIM NO-DIM 3300700500017 0.908 0.025 3300700500018 ENDDATA 3 0 3300700500019 ENDSUBENT 18 0 3300700599999 ENDENTRY 5 0 3300799999999