Abstract: The object of the invention relates to a neutron absorbing concrete wall (10), which concrete wall (10) has an internal delimiting surface (11a), and an external delimiting surface (11b) on an opposite side to the internal delimiting surface (11a), the essence of which is that it contains a first concrete layer (13a) on the side of the internal delimiting surface (11a), and a second concrete layer (13b) on the side of the external delimiting surface (11b), which first concrete layer (13a) contains at least 0.05 mass % boron-10 isotope (10B), and the second concrete layer (13b) is formed as heavyweight concrete. The object of the invention also relates to a method for creating a neutron radiation absorbing concrete wall (10) that has an internal delimiting surface (11a), and an external delimiting surface (11b) on an opposite side to the internal delimiting surface (11a), the essence of which is a first concrete layer (13a) containing at least 0.

Abstract: The object of the invention relates to a neutron absorbing concrete wall (10), which concrete wall (10) has an internal delimiting surface (11a), and an external delimiting surface (11b) on an opposite side to the internal delimiting surface (11a), the essence of which is that it contains a first concrete layer (13a) on the side of the internal delimiting surface (11a), and a second concrete layer (13b) on the side of the external delimiting surface (11b), which first concrete layer (13a) contains at least 0.05 mass % boron-10 isotope (10B), and the second concrete layer (13b) is formed as heavyweight concrete. The object of the invention also relates to a method for creating a neutron radiation absorbing concrete wall (10) that has an internal delimiting surface (11a), and an external delimiting surface (11b) on an opposite side to the internal delimiting surface (11a), the essence of which is a first concrete layer (13a) containing at least 0.

Abstract: A method including providing a nuclear reactor neutron source that includes an enclosure delimiting a chamber, a nuclear reactor core arranged inside the chamber and configured to produce neutrons from a nuclear fuel element inside the nuclear reactor core; installing a beam generator arranged to generate a beam directed into the chamber; and installing, inside the chamber, a target arranged to eject neutrons upon impact of the beam such that neutrons are ejected from the target and emitted from the chamber.

Abstract: A method for providing a neutron source. The method including: providing a nuclear reactor neutron source, the nuclear reactor neutron source including: an enclosure delimiting a chamber, a nuclear reactor core arranged inside the chamber, the nuclear reactor core is configured to produce neutrons from a nuclear fuel element inside the nuclear reactor core; installing a beam generator arranged to generate a beam directed into the chamber; and installing, inside the chamber, a target arranged to eject neutrons upon impact of the beam such that neutrons are ejected from the target and emitted from the chamber.

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 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.