7 results about "Spent nuclear fuel" patented technology

The application belongs to the technical field of separation and extraction, and particularly relates to a 8C-DAPhen ligand, a preparation method and application thereof. The method is developed from the design of a ligand molecular structure, and a novel cyclic DAPhen ligand is developed through specific structure design. The ligand has a separation factor (SF Eu / Am ) of more than 600 for lanthanide and actinide elements, and exhibits excellent separation performance. The application provides a new perspective for in-depth understanding of lanthanide and actinide separation mechanism, and provides technical support for establishing an advanced spent nuclear fuel reprocessing system and realizing efficient utilization of minor actinide elements.

Proposed is a cutting apparatus for a fuel basket accommodating spent nuclear fuel of a heavy water reactor, wherein the apparatus includes a base, a vertical support arranged on one side of the base; a turn table arranged to be reciprocated between one side and an opposite side of the base and be horizontally rotatable on the base; a horizontal support arranged to extend from an upper-end of the vertical support in a horizontal direction toward the turn table; a side-cutting means arranged on the vertical support protruding toward the turn table for cutting a side welding bead of the fuel basket mounted on the turn table; and an upper-cutting means arranged on the horizontal support protruding toward the turn table for cutting an upper welding bead of the fuel basket mounted on the turn table.

The application belongs to the technical field of extraction separation, and particularly relates to an OE-DAPhen ligand, a preparation method and application thereof. The application develops a novel DAPhen ligand through specific structure design from the design of a ligand molecular structure. The separation factor (SF) of the OE-DAPhen ligand for lanthanide and actinide elements is more than 400, and the OE-DAPhen ligand exhibits excellent separation performance. The application provides a new perspective for in-depth understanding of lanthanide and actinide separation mechanism, and provides technical support for establishing an advanced spent nuclear fuel reprocessing system and realizing efficient utilization of minor actinide elements. Eu / Am ).

Disclosed herein is a system comprising: (a) an experimentation cask having a receiving compartment defining an internal portion of the experimentation cask, wherein the receiving compartment is configured to receive a canister, wherein the canister is a vertical and / or horizontal spent fuel storage canister, (b) one or more sensing devices configured to non-destructively evaluate an internal and / or external state of the canister; wherein the one or more sensing devices are positioned within at least a portion of the internal portion of the experimentation cask, or at least a portion of an external portion of the experimentation cask; and wherein the experimentation cask provides radiation- and heat shielded. Also disclosed herein are methods for inspection of an internal and external integrity of the canister using the systems disclosed herein.

Device for reducing spent nuclear fuel, comprising a container for receiving nuclear fuel, wherein the device is configured to transmute long-lived radioisotopes of the nuclear fuel into radioisotopes having a significantly shorter half-life than the initial radioisotopes by interaction with fast neutrons.

Calorimeter for measuring the linear residual power of at least a portion or piece of a spent or new nuclear fuel rod. The invention essentially consists of a calorimeter whose core is delimited by a block of radioactive and thermal radiation-absorbing material surrounded by a housing of thermal insulation material that thermally isolates the core from the ambient environment. The block and the housing are each in two parts that can be separated for the easy and rapid insertion of a spent fuel rod. The calorimeter is instrumented with temperature sensors distributed along its length, which are inserted into the block and / or the housing to measure the linear residual power of the inserted fuel rod. Figure for the abstract: Fig. 2A