초록 ▼

This invention relates to a standard component 99mTC elution generator useful for medical purposes and consisting of prefabricated component parts. The main generator column of the device may be used both as an irradiation container and an elution container, enabling the user to supply activated or

This invention relates to a standard component 99mTC elution generator useful for medical purposes and consisting of prefabricated component parts. The main generator column of the device may be used both as an irradiation container and an elution container, enabling the user to supply activated or nonactivated parts. The main generator column made from by neutrns little activable materials serves first as reactor irradiation ampoule and after having been activated in the reactor by neutrons and after a simple adjustment serves directly as the generator column. It is filled with water insoluable molybdates or polymolybdates (with the molybdenum content in the range 10-40%), easily releasing 99mTc generated by radioactive decay of the mother 99Mo formed in it by neutron activation. This column filling serves originally as target material for reactor irradiations and afterwards it is directly used as the generator elution matrix. Accordingly, all components of the generator can be produced in a “ready-to-use”form and supplied as inactive material. When nonactivated parts are used, activation is performed on-site by a local reactor. The use of nonactivated parts is advantageous because they are more easily and more safely manufactured and transported. The invention further provides for efficient generation of 99mTC radionuclides from medium neutron flux irradiation of molybdenum in a natural isotopic mixture.

대표청구항 ▼

A method of preparation of 99mTc elution comprising the steps of, filling a main column composed of a material selected from the group consisting of aluminum, zirconium, quartz, carbon and oxides thereof with a target material comprising at least 10% by weight of molybdenum; plugging the ends of the

A method of preparation of 99mTc elution comprising the steps of, filling a main column composed of a material selected from the group consisting of aluminum, zirconium, quartz, carbon and oxides thereof with a target material comprising at least 10% by weight of molybdenum; plugging the ends of the main column with a porous material; closing the ends of the main column; wrapping the ends of the main column to protect against secondary bacterial contamination; activating the target material to form a 99Mo containing sorption matrix accompanied simultaneously by radiation sterilization of the main generator column and its contents by exposure to neutron and accompanied gamma radiation in a reactor; opening the ends of the main generator column in sterile environment under aseptic conditions of manipulation; connecting a supply tube to one end of the main column and a discharge tube to the other end in a sterile manner; placing the main column, supply tube, and discharge tube in a transport container composed of a material selected from the group consisting of lead or depleted uranium; placing the transport container in a laboratory container, the laboratory container also housing an elution vessel, a protective column, and at least one eluate collection bottle; connecting the supply tube to an elution vessel in a sterile manner, the elution vessel containing an elution solution; connecting the discharge tube to one end of a protective column in a sterile manner, the other end having a piercing head; piercing the seal of an evacuated eluate collection bottle with the piercing head; drawing the eluation solution through the supply tube, main column containing the sorption matrix, discharge tube, and protective column, and into the eluate collection bottle, the eluate containing 99mTc.