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1. RI Production
I-131 Solution and Capsules
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HANARO and dry process were utilized for the production of I-131 from 1997 and the encapsulation process was developed by KAERI. Now KAERI produces and supplies the I-131 solution of specific activity of 2~4 Ci/ml and therapeutic capsules of 30 to 200 mCi to domestic users.
To meet the increasing demand of high dose I-131 therapy for cancer treatment, four batch operations per week, the installation of stand-by equipment in chemical processing, and process automation will be tried. The maximum capacity of I-131 production will be 60 Ci/week.
Export of I-131 products to foreign markets is also considered in near future.
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Ir-192 radiation Sources
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In 1997, the equipment for the fabrication of the radiographic sources was installed at concrete hot cell of the RIPF. After obtaining the license for Ir-192 production, around 3,000 Ci/month of Ir-192 sources will be produced and fabricated.
Ir-192 irradiators for NDT use are being developed using depleted uranium for more effective utilization of the source. All the technologies for the production of Ir-192 sources will be transferred to a private company. The company will produce and supply the NDT sources to domestic users and foreign markets.
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Various R&D activities are made to develop new radioisotopes which would satisfy expanding needs in science and technology as well as in medicine.
The production process of high quality I-125, Sr-89, p-33 and technologies for preparing W-188/Re-188 generator are also under development.
In addition, research has been extended to develop the low energy g-ray emitting sources, such as Yb-169, Se-75, which would be used in non-destructive testing application.
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RI Labelling and Application
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New Radiotherapeutic Agents of Holmium-166
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166Ho has a 26.8-hour half-life and decays with the emission of high-energy b particles with energies of 1.77 MeV (48 %) and 1.85 MeV (51%), and with the emission of one gamma photon with an energy of 80.5 keV suitable for gamma imaging. Newly-developed therapeutic agents using 166Ho are 166Ho-chitosan complex for liver cancer treatment, the 166Ho patch for skin cancer treatment and devices for brachytherapy such as the stent and balloon for prevention of restenosis of coronary artery. While the stent and the balloon are still under development, pre-clinical studies on 166Ho-chitiosan complex and the 166Ho patch have been completed with very successful results and clinical studies are now being carried out at various hospitals
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Treatment of
hepatocellular
carcinoma with 166Ho-CHICO which
was adminstered via the
intrahepatic
artery. |
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The characteristics of 166Ho-CHICO are found to be similar to those of chitosan, which is biocompatible, biodegradable, non-toxic, soluble and viscous in acidic conditions, but gel-forming at pH 6.0 and precipitating in alkaline condition. A biodistribution study using a gamma camera in normal rabbits showed that most of the radioactivities are retained in the knee joint with negligible extra-articular leakage at even 72 hours after intra-articular administration. Clinical trials with 166Ho-CHICO in the treatment of liver cancer, peritoneal cancer metastasized from ovarian and stomach cancer, cystic brain tumor and rheumatoid arthritis in knee joints are being carried out.
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o A typical 166Ho-Patch
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The radioactive patch practically
applicable to the treatment of the
superficial skin cancer can be prepared
as a sandwich type patch
by inserting
the 166Ho-film between two polyester
film layers. Skin tumors can be
successfully treated with the
166Ho-patch in animal models and
patients. The ease with which the
166Ho-patch can be prepared in various
types, and also its safety and
effectiveness, make it an attractive
device for skin cancer treatment.
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We have developed a new radioactive stent comprising of a radioactive tubular sleeve covering a metallic stent. Scanning electron microscopy and autoradiography showed that the distribution of 165/166Ho(NO3)3 compounds in a polyurethane matrix was homogeneous. The total dose rate of 166Ho-stent with a diameter of 20 mm and length of 40 mm due to b-particles and g-rays was 1.8570 cGy/s per GBq at a 0.0 – 0.5 mm target depth. In an animal experiment, when the radioactive stent developed was inserted into the esophagus of a Mongrel dog, tissue destruction and widening of the esophageal lumen were observed.
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o Existed balloon with inner volume of
about 0.2 mL, which is filled with
166Ho-DTPA.
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The labelling yield of 166Ho-DTPA was 100 % when the ratio of DTPA to 166Ho was 4 to 1, and a high radiochemical purity (>99.5%) was maintained at room temperature for 24 hours. The renograms of rabbits obtained using gamma camera imaging showed that 166Ho-DTPA was quickly excreted via the urinary system within 30 min after administration. The ease with which 166Ho-DTPA can be prepared from a kit form with high radioactivity concentrations ( 3.7-7.4 GBq/ml (100-200 mCi/ml)) and its fast urinary excretion make it an efficient liquid radiation source for radiation brachytherapy in the restenosis of the coronary artery using a liquid-filled balloon
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A new radioactive coated balloon prevents tumor ingrowth and restenosis by additional radiation treatment. It is developed for the purpose of reduction of unnecessary radioactivity within a syringe and catheter and the delivery of sufficient radiation to the vessel wall. It is prepared by coating the surface of an existing balloon with 166Ho instead of being filled with beta sources. The coating material is similar to that of an 166Ho-patch.
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List of Radioisotope Products
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Classification
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Completed
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Under development
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Radioisotopes
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Open
source
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Tc-99m I-131
Au-198
Cr-51
P-32
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Re-186 Re-188
P-33
Mo-99/Tc-99m
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Sealed
source
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Ir-192
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Gd-153 Eu-152
Sb-125
Ni-63
Co-60
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Radiolabeled
compound
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I-131
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Hipuran MIBG
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Tc-99m
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Phytate MDP
DISIDA DTPA
PTP
Sn colloid
HSA
MAA
ASC
DMSA
HMPAO
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CNS receptor of neurotransmitter
imaging agent
Tumor imageing
agent
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Dy-165
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HMA MA
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Ho-166
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DTPA CHICO
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Sm-153
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CHICO EDTMP
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Er-169
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CHICO
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Others
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Ho-166
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Patch Stent Ballon
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Medical radioisotopes, such as I-131, Tc-99m, Ho-166, are routinely produced and supplied to domestic users.
Sealed sources for industrial and medical uses are Ir-192 and Co-60. Several hundreds Curies of these nuclides, has been supplied to domestic users.
KAERI will enlarge the supply of national RI demand and export them to foreign countries. We have a long-term plan to construct a new reactor fully dedicated to radioisotope production for steady and reliable RI supply.
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