Abstract: The radionuclide 43Sc is produced at commercially significant yields and at specific activities and radionuclidic purities which are suitable for use in radiodiagnostic agents including imaging agents. In a method, a solid target having an isotopically enriched target layer prepared on an inert substrate is positioned in a specially configured target holder and irradiated with a charged-particle beam of protons or deuterons. The beam is generated using an accelerator such as a biomedical cyclotron at energies ranging from 3 to about 22. MeV. The method includes the use of three different nuclear reactions: a) irradiation of enriched 43Ca targets with protons to generate the radionuclide 43Scin the nuclear reaction 43Ca (p,n)43Sc, b) irradiation of enriched 42Ca targets with deuterons to generate the radionuclide 43Sc in the nuclear reaction 42Ca(d,n)43Sc, and c) irradiation of enriched 46Ti targets with protons to generate the radionuclide 43Sc in the nuclear reaction 46Ti (p,a) 43Sc.

Abstract: The radionuclide 43Sc is produced at commercially significant yields and at specific activities and radionuclidic purities which are suitable for use in radiodiagnostic agents including imaging agents. In a method, a solid target having an isotopically enriched target layer prepared on an inert substrate is positioned in a specially configured target holder and irradiated with a charged-particle beam of protons or deuterons. The beam is generated using an accelerator such as a biomedical cyclotron at energies ranging from 3 to about 22 MeV. The method includes the use of three different nuclear reactions: a) irradiation of enriched 43Ca targets with protons to generate the radionuclide 43Scin the nuclear reaction 43Ca (p,n)43Sc, b) irradiation of enriched 42Ca targets with deuterons to generate the radionuclide 43Sc in the nuclear reaction 42Ca(d,n)43Sc, and c) irradiation of enriched 46Ti targets with protons to generate the radionuclide 43Sc in the nuclear reaction 46Ti (p,a)43Sc.

Abstract: The radionuclide 43Sc is produced at commercially significant yields and at specific activities and radionuclidic purities which are suitable for use in radiodiagnostic agents including imaging agents. In a method, a solid target having an isotopically enriched target layer prepared on an inert substrate is positioned in a specially configured target holder and irradiated with a charged-particle beam of protons or deuterons. The beam is generated using an accelerator such as a biomedical cyclotron at energies ranging from 3 to about 22 MeV. The method includes the use of three different nuclear reactions: a) irradiation of enriched 43Ca targets with protons to generate the radionuclide 43Scin the nuclear reaction 43Ca (p,n)43Sc, b) irradiation of enriched 42Ca targets with deuterons to generate the radionuclide 43Sc in the nuclear reaction 42Ca(d,n)43Sc, and c) irradiation of enriched 46Ti targets with protons to generate the radionuclide 43Sc in the nuclear reaction 46Ti (p,a)43Sc.

Abstract: The present invention relates to an universal method for the large scale production of high-purity carrier free or non carrier added radioisotopes by applying a number of “unit operations” which are derived from physics and material science and hitherto not used for isotope production. A required number of said unit operations is combined, selected and optimized individually for each radioisotope production scheme. The use of said unit operations allows a batch wise operation or a fully automated continuous production scheme. The radioisotopes produced by the inventive method are especially suitable for producing radioisotope-labelled bioconjugates as well as particles, in particular nanoparticles and microparticles.

Abstract: The invention is directed to a method for the purification of Radium, in particular 226Ra, for target preparation for an essentially pure 225Ac production from available radioactive sources, using an extraction chromatography in order to separate chemically similar elements such as Ba, Sr, and Pb from the desired Ra; wherein said extraction chromatography has an extractant system on the basis of a crown ether. The invention is related to a method for recycling of 226Ra, for target preparation for 225Ac production from radium sources irradiated with accelerated protons (p,2n), after separation of the produced 225Ac. In this method a combination of the above extraction chromatography and a cation exchange chromatography is used. The obtained 226Ra is essentially free of the following chemical contaminants consisting of Ag, Al, As, Be, Bi, Ca, Cd, Co, Cr, Cu, Fe, Ga, K, Li, Mg, Mn, Na, Ni, Pb, Sr, V, Zn, and Ba.

Abstract: The invention is directed to a method for the purification of Radium, in particular 226Ra, for target preparation for an essentially pure 225Ac production from available radioactive sources, using an extraction chromatography in order to separate chemically similar elements such as Ba, Sr, and Pb from the desired Ra; wherein said extraction chromatography has an extractant system on the basis of a crown ether. The invention is related to a method for recycling of 226Ra, for target preparation for 225Ac production from radium sources irradiated with accelerated protons (p,2n), after separation of the produced 225Ac. In this method a combination of the above extraction chromatography and a cation exchange chromatography is used. The obtained 226Ra is essentially free of the following chemical contaminants consisting of Ag, Al, As, Be, Bi, Ca, Cd, Co, Cr, Cu, Fe, Ga, K, Li, Mg, Mn, Na, Ni, Pb, Sr, V, Zn, and Ba.

Abstract: The invention provides a method for suppressing postoperative ileus in connection with the performance of a surgical procedure on a patient. In accordance with the inventive method, interleukin-10 (IL-10), glycine, a COX-2 inhibitor and a mast cell stabilizer are administered to the patient undergoing the surgical procedure in an amount and at a location sufficient to therapeutically or prophylactically suppress postoperative ileus in the patient. The invention further provides a pharmaceutically acceptable composition comprising interleukin-10 (IL-10), glycine, a COX-2 inhibitor, a mast cell stabilizer and a pharmaceutically-acceptable carrier.

Abstract: The present invention relates to an universal method for the large scale production of high-purity carrier free or non carrier added radioisotopes by applying a number of “unit operations” which are derived from physics and material science and hitherto not used for isotope production. A required number of said unit operations is combined, selected and optimised individually for each radioisotope production scheme. The use of said unit operations allows a batch wise operation or a fully automated continuous production scheme. The radioisotopes produced by the inventive method are especially suitable for producing radioisotope-labelled bioconjugates as well as particles, in particular nanoparticles and microparticles.