ENTRY B0118 20211221 B032B011800000001 SUBENT B0118001 20211221 B032B011800100001 BIB 16 102 B011800100002 TITLE Relative thresholds for production of iodine B011800100003 isotopes from fusion and transfer-induced fission B011800100004 reactions. B011800100005 AUTHOR (M.De Saint-Simon, R.J.Otto, G.T.Seaborg) B011800100006 INSTITUTE (2FR PAR,1USABRK) B011800100007 Laboratoire Rene Bernas, Orsay. B011800100008 REFERENCE (J,PR/C,18,1651,1978) B011800100009 FACILITY (LINAC,1USABRK).Super HILAC facility. B011800100010 Since the heavy ion beam was not magnetically analyzed,B011800100011 the beam energies were measured with a gold B011800100012 surface-barrier detector placed directly in the beam B011800100013 path. B011800100014 METHOD (SITA,EXTB,BCINT,CHSEP) B011800100015 chemical separation of iodine was done within B011800100016 10 minutes of the end of bombardment. The length B011800100017 of bombardment was different for the used projectile B011800100018 energies and lasted from 63 minutes to 212 minutes. B011800100019 An silver-iodide/silver-bromide precipitate was B011800100020 obtained and after filtering, both PRECPITATE and B011800100021 filter paper were taped to a holder and placed in B011800100022 front of a Ge(Li)-spectrometer. B011800100023 The U-layer was dissolved together with part of the B011800100024 Al-backing plate to ensure dissolution of all of the B011800100025 fission products. B011800100026 The chemical yield was determined by neutron activationB011800100027 of I-127 in the samples and in a standard. B011800100028 The samples were counted, starting approximately B011800100029 10 minutes after the end of bombardment and B011800100030 extending to 2 to 3 weeks thereafter. B011800100031 The average beam flux was 2.6*10**11 particles/sec. B011800100032 SAMPLE Enriched U-238 targets, thickness 30 mg/cm**2. B011800100033 U-238 was sputtered onto a 5 mm Al-backing plate. B011800100034 a thin layer of 50-100 microgram/cm**2 Al was B011800100035 evaporated onto the surface of the U-238 to prevent B011800100036 oxidation. An effective target thickness was B011800100037 calculated,using the tables of Northcliffe and B011800100038 schilling, NUCL.DATA tables A7,233(1970), and B011800100039 corresponds to the range of Ar-40 ions slowed down fromB011800100040 the incident energy to the barrier that was taken to B011800100041 be 200 MeV. B011800100042 PART-DET (DG). The gamma ray spectra were recorded between B011800100043 90 keV and 2 MeV. B011800100044 DETECTOR (GELI) B011800100045 the absolute efficiency for the counting geometry B011800100046 was known with an accuracy of 5%. B011800100047 ERR-ANALYS (DATA-ERR) The given uncertainties in the production B011800100048 cross sections reflect the errors in the half-life fitsB011800100049 to the data. They vary between 1% and 20% (comment byB011800100050 the compiler of KACHAPAG). Further information about B011800100051 the errors are missing. B011800100052 2. The errors in beam energy were +-5 MeV, including B011800100053 a possible energy shift of +-4 MeV and corrections B011800100054 for energy loss in the Al-layer and energy defect B011800100055 in the surface-barrier detector. B011800100056 The corrections to the beam energy consisted in B011800100057 adding 1.0 to 1.5 MeV to the measured energies B011800100058 which was less than the uncertainty in B011800100059 the beam energy. B011800100060 ANALYSIS (DECAY)The identification and assignment of a nuclide B011800100061 was based on agreement of the energy, half-life and B011800100062 relative abundance of the observed gamma-rays. B011800100063 In order to calculate independent yields from the B011800100064 measured partial cumulative ones it was concluded from B011800100065 the two-peaked isotopic distributions that the neutron B011800100066 excessive fission products originate from quasi-elasticB011800100067 transfer induced fission of uranium, while the neutron B011800100068 deficient and shielded products near the stability lineB011800100069 are due to complete fusion followed by fission of the B011800100070 compound nucleus. Basing on this interpretation the B011800100071 independent yield distribution was calculated by an B011800100072 iterative procedure. B011800100073 CORRECTION The data were corrected for recoil losses from B011800100074 the surface of the target corresponding to fission B011800100075 fragments moving backward in the laboratory reference B011800100076 frame. The recoil losses were calculated from B011800100077 theoretical distributions of the products for the B011800100078 different mechanisms involved and were then integrated B011800100079 over the effective target thickness, taking also into B011800100080 account the decreasing bombarding energies. B011800100081 ADD-RES (THEO) B011800100082 the thresholds for production of iodine isotopes B011800100083 either by complete fusion reactions or by B011800100084 QUASIELASTIC transfer reactions are determined and B011800100085 compared with theoretical predictions. B011800100086 COMMENT - by compiler of CAJAD - presented cross sections are B011800100087 average for effective target thickness. B011800100088 - by authors - B011800100089 beam energy effective target thickness B011800100090 MeV MILLIGRAMM/cm**2 B011800100091 212. 1.0 B011800100092 226. 3.0 B011800100093 240. 6.0 B011800100094 250. 8.0 B011800100095 270. 11.0 B011800100096 290. 15.5 B011800100097 340. 26.0 B011800100098 STATUS (TABLE) Table II of Phys.Rev.C18(1978)1651. B011800100099 HISTORY (19800130C)NEKW B011800100100 (19981218A) Lower case. B011800100101 (20011010U) Last checking has been done. B011800100102 (20211221A) VS. Status added. B011800100103 Reaction and data correction in 002-003. B011800100104 ENDBIB 102 0 B011800100105 NOCOMMON 0 0 B011800100106 ENDSUBENT 105 0 B011800199999 SUBENT B0118002 20211221 B032B011800200001 BIB 2 8 B011800200002 REACTION 1(92-U-238(18-AR-40,F)ELEM/MASS,,SIG,,AV) B011800200003 2(92-U-238(18-AR-40,F)ELEM/MASS,,SIG,,AV/REL) B011800200004 relative data because the absolute intensity of the B011800200005 beam flux at an incident energy of 340 MeV was B011800200006 unknown. B011800200007 HISTORY (20211221A) VS reaction: IND,SIG,,REL/AV,EXP B011800200008 replaced with IND,FY,,REL in 002.2; SF9: EXP deleted. B011800200009 Data: theoretical values deleted. COMMENT deleted. B011800200010 ENDBIB 8 0 B011800200011 NOCOMMON 0 0 B011800200012 DATA 7 14 B011800200013 EN ELEMENT MASS DATA 1DATA-ERR 1DATA 2B011800200014 DATA-ERR 2 B011800200015 MEV NO-DIM NO-DIM MB MB ARB-UNITS B011800200016 ARB-UNITS B011800200017 240. 53. 124. 0.683 0.028 B011800200018 B011800200019 240. 53. 126. 2.340 0.069 B011800200020 B011800200021 250. 53. 124. 1.241 0.287 B011800200022 B011800200023 250. 53. 126. 3.545 0.045 B011800200024 B011800200025 250. 53. 128. 3.118 0.031 B011800200026 B011800200027 270. 53. 124. 1.65 0.19 B011800200028 B011800200029 270. 53. 126. 4.34 0.24 B011800200030 B011800200031 270. 53. 128. 3.77 0.038 B011800200032 B011800200033 290. 53. 124. 3.00 0.23 B011800200034 B011800200035 290. 53. 126. 7.17 0.07 B011800200036 B011800200037 290. 53. 128. 5.51 0.06 B011800200038 B011800200039 340. 53. 124. 2.64B011800200040 0.13 B011800200041 340. 53. 126. 5.64B011800200042 0.58 B011800200043 340. 53. 128. 4.52B011800200044 0.22 B011800200045 ENDDATA 32 0 B011800200046 ENDSUBENT 45 0 B011800299999 SUBENT B0118003 20211221 B032B011800300001 BIB 2 8 B011800300002 REACTION 1(92-U-238(18-AR-40,F)53-I-130-G,M+,SIG,,AV) B011800300003 2(92-U-238(18-AR-40,F)53-I-130-G,M+,SIG,,AV/REL) B011800300004 relative data because the absolute intensity of the B011800300005 beam flux at an incident energy of 340 MeV was B011800300006 unknown. B011800300007 HISTORY (20211221A) VS. REACTION: IND/M+,SIG,,REL/AV,EXP B011800300008 replaced with IND,FY,,REL in 003.2; SF9: EXP deleted. B011800300009 DATA: theoretical values deleted. COMMENT deleted. B011800300010 ENDBIB 8 0 B011800300011 NOCOMMON 0 0 B011800300012 DATA 5 7 B011800300013 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 B011800300014 MEV MB MB ARB-UNITS ARB-UNITS B011800300015 212. 0.184 0.004 B011800300016 226. 0.952 0.064 B011800300017 240. 2.29 0.15 B011800300018 250. 3.214 0.098 B011800300019 270. 3.65 0.16 B011800300020 290. 5.39 0.17 B011800300021 340. 4.55 0.28 B011800300022 ENDDATA 9 0 B011800300023 ENDSUBENT 22 0 B011800399999 ENDENTRY 3 0 B011899999999