343 results about "Radiogenic nuclide" patented technology

The invention discloses a method for preparing radioactive <124>I ions. The preparation method comprises the following steps: a, taking aluminium oxide powder and tellurium dioxide powder in a mass ratio of 1:18-22, uniformly mixing the powder, and pressing the obtained mixture into a tellurium target with a thickness of 50-60 mg/cm<2>; b, placing the prepared tellurium target in a circular accelerator, and irradiating the tellurium target 2-3 h by Te (p, n) <124>I, wherein the incident p particle beam intensity is 18-20 mu A, the energy is 18.5-20 MeV, and the angle of incidence is 6-10 DEG; meanwhile, cooling the tellurium target by using water in the process of irradiating, and after the irradiating is completed, placing the tellurium target to cool 4-6 h; c, placing the tellurium target in a quartz distillation tube of a destructive distillation device to distill, meanwhile, controlling the temperature to 750 DEG C so as to heat the tellurium target, so that radioactive <124>I ions are escaped, and collecting the radioactive <124>I ions. The problems that radionuclide <124>I prepared in the prior art is low in yield and low in recovery rate are solved.

The present invention relates to a method and apparatus for simultaneous quantification of the amounts of one or more radioactive nuclides within arbitrary regions on a surface where these nuclides have been deposited, adsorbed or fixed. These radioactive nuclides serve as markers on compounds that typically have been incorporated into tissue sections or into larger biological molecules that by various mechanisms have been bound to chemical substances on this surface. The method is especially well suited for DNA microarray deductions through the use of nucleotides labelled with different beta-emitting radionuclides.

The present invention relates to radionuclide complex solutions of high concentration and of high chemical stability, that allows their use as drug product for diagnostic and/or therapeutic purposes. The stability of the drug product is achieved by at least one stabilizer against radiolytic degradation. The use of two stabilizers introduced during the manufacturing process at different stages was found to be of particular advantage.

The invention discloses a derivate for labeling bile acid shown in formula VI, wherein A is -(CH2CH2)x- or -(CH2CH2O)m(CH2CH2)n-, x=1-4, preferably 1 or 3, m=1-3, preferably 1, n=1, and R1,R2 and R3 are hydrogen, alpha-OH or beta-OH respectively. The invention also provides a reference compound, a preparation method and an application of the derivate for labeling bile acid. The invention utilizes radioactive nuclide 99mTc to indirectly label bile acid for the first time, and the derivate for labeling bile acid in the invention has good application prospect of raster display.

The invention discloses a radioactive wastewater adsorption filter. The operation of replacing a filter bag is rapid and convenient; a compressing assembly is automatically loosened only by opening a top cover; after the compressing assembly is taken away, the filter bag filled with a filter material is rapidly lifted out from the upper part and a new filter bag with the filter material is put in again; and then, the compressing assembly is put back, the top cover is closed and the new absorption can be started. The filter bag is rapidly replaced to reduce the radiation on personnel to a maximum extent. Aiming at special nuclides, the filter bag with a characteristic absorption material is chosen or replaced, so that the removal rate of radioactive nuclides can be effectively improved. In addition, in an adsorber, a coupling layer capable of being compressed surrounds and tightly covers the external side face of the filter bag, so that the radioactive wastewater flows through the filter bag from top to bottom after entering a drum body via a water inlet at the upper part, and flows out of drain meshes at the bottom of the filter bag and the bottom of a fixing frame; the outflow at the side face of the filter bag is avoided, that is, the short-circuit current is avoided; the radioactive wastewater sufficiently flows through the filter bag from top to bottom, so that the nuclides in the wastewater are completely adsorbed by the filter material in the filter bag and the nuclides in the wastewater are removed thoroughly.