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SIMULATIONS ON NICKEL TARGET PREPARATION AND SEPARATION OF Ni(II)- Sunarhadijoso Soenarjo; Wira Rahman; Sriyono Sriyono; Triyanto Triyanto
GANENDRA Majalah IPTEK Nuklir Volume 14 Nomor 1 Januari 2011
Publisher : Website

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (211.268 KB) | DOI: 10.17146/gnd.2011.14.1.26

Abstract

SIMULATIONS ON NICKEL TARGET PREPARATION AND SEPARATION.OF Ni(II)-Cu(II) MATRIX FORPRODUCTION OF RADIOISOTOPE64Cu64Ni (p,n) 64  and retained on the column while the nickel was kept in the form of Ni2+  2+  2+ and CuCl while the nickel was totally in the form of Ni2+  while the nickel was found as both Ni2+ and NiCl   while the nickel was mostly in the form of Ni2+. The retained CuCl was then changed back into Cu2+     Keywords 64 Cu, Anion exchange chromatography.: Nickel target preparation, Radioisotope Cu-64, Separation of Ni(II)-Cu(II) matrix, Nuclear reaction of 64Ni(p,n) cation form andeluted out the column by using HCl 0.05 M. The 42– 4 2–.The best condition of separation was in HCl 8 M in which the radioactive copper was mostly in the form of CuCl 42– 42– . In the condition ofHCl 9 M, the radioactive copper was mostly in the form of CuCl 42– cation. It was found that the electroplating result from the acidic solution was more satisfied than that from the basic solution. By conditioning the matrix solution at HCl 6 M, the radioactivecopper was found in the forms of Cucation and eluted off from the column. The retained radioactive copper was then eluted out the column in the condition of dilute HCl changingback the copper anion complex into Cu42– Cu. The nickel target preparation was performed by means of electroplating method using acidic solution of nickel chloride - boric acid mixture and basic solution of nickel sulphate – nickel chloridemixture on a silver- surfaced-target holder. The simulated solution of Ni(II) – Cu(II) matrix was considered as thesolution of post-proton-irradiated nickel target containing both irradiated nickel and radioactive copper, but in thepresented work the proton irradiation of nickel target was omitted, while the radioactive copper was originallyobtained from neutron irradiation of CuO target. The separation of radioactive copper from the nickel target matrixwas based on anion exchange column chromatography in which the radiocopper was conditioned to form anioncomplex CuClg-spectrometric analysis showed a single strong peak at 511 keVwhich is in accord to g-annihilation peak coming from positron decay of Cu-64, and a very weak peak at 1346 keVwhich is in accord to g-ray of Cu-64.. The simulations on Nickel target preparation and separation of Ni(II)- Cu(II) matrix has been carried out as a preliminary study for production of medical radioisotope Cu-64 based onnuclear reaction of
PERBANDINGAN Cr-51 (III) DAN Cr-S1 (VI) ANORGANIK PADA HASIL IRADIASI Cr(CO)s DAN Cr(C5H7O2)3 DENGAN NEUTRON TERMAL Sunarhadijoso Soenarjo; Said Adam; Iswandi Idris
Jurnal Kimia Terapan Indonesia Vol 2, No 1-2 (1992)
Publisher : Research Center for Chemistry - LIPI

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (2731.798 KB) | DOI: 10.14203/jkti.v2i1-2.288

Abstract

Thermal neutron irradiation on Cr(CO)6 and Cr(C5H7O2)3 target compounds had been conducted with an average neutron flux of about 2.8 x 10(12) n.cm(-2).der(1). Both post-irradiated target compounds gave inorganic radiochromium in oxidation states of +3 and +6 which were separated by solvent extraction method: For radioactivity measurement, the trivalent species was separased from the hexavalent by hydroxide precipitation using K2CrO4 and Cr(NO)3. 9H2O carriers. The inorganic chromium content was chemically determined by spectrophotometric method without adding arry carriers. The activity of the trivalent inorganic chromium produced from Cr(CO)6 irradiation was higher than that of the hexavalent ones, but in the case of Cr(C5H7O2)3 irradiation; the activity of the hexavalent species was higher. In both cases, the specific activity of the trivalent species was higher than that of the hexavalent species. The specific activity of total inorganic chromium obtained from the irradiation of Cr(CO)6 was higher than that of Cr(C5H7O2)3.
RADIONUCLIDIC IMPURITIES IN PERTECHNETATE SOLUTION ELUTED FROM 99mTc-CHROMATOGRAPHIC GENERATOR LOADED WITH 99Mo-FISSION PRODUCT Sunarhadijoso Soenarjo; Adang Hardi Gunawan
Jurnal Kimia Terapan Indonesia Vol 7, No 1-2 (1997)
Publisher : Research Center for Chemistry - LIPI

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (3245.144 KB) | DOI: 10.14203/jkti.v7i1-2.222

Abstract

Medical radioisotope of 99mTc was firstly produced in Indonesia through the nuclear reaction of 98Mo (n;y) 99Mo -> 99mTc. The separation of the resulting 99mTc from the postirradiated natural MoO3 was carried out by solvent extraction using methyl ethyl ketone. Instead of this method, Radioisotope Production Center (RPC) BATAN has routinely produced 99mTc-chromatographic generator loaded with 235U-flSsion-produced 99Mo to provide 99mTc. By such generator, 99mTc can be easily and repeatedly liberated in the form of pertechnetate by vacuum elution using saline solution. Some fission- produced radionuclides, however, potentially contaminate the pertechnetate fraction. Gamma spectrometric determination was carried out to evaluate the level of radionuclidic impurities contaminating 99mTc-pertechnetate solution eluted from 99mTc- chromatographic generator produced over a 10-month period in 1993 - 1994. Radioactivity yield of the resulting 99mTc was independent to the origin of the loaded 99Mo. The 99mTc-pertechnetatate fractions were frequently contaminated with 99Mo, 131I and 103Ru, but the contamination did not exceed maximum permissible level. The fluctuation of contamination level may be influenced by irradiation parameters and separation techniques applied to the production of the loaded 99Mo.