Method and System for Disposing and Recycling of a Radioactive Contaminated Component

Simple SummaryContent extracted from patent full text and abstract with AI.

This invention provides a method and system for safely disposing of and recycling radioactive components found in nuclear power plants, notably graphite moderators. The process involves burning the contaminated graphite under controlled high temperatures, converting it to a gas mixture that mainly includes carbon monoxide. This mixture is then carefully separated into radioactive and non-radioactive carbon monoxide, reducing the volume of highly radioactive waste and enabling much of the material to be safely recycled or repurposed.

Use CasesContent extracted from patent full text and abstract with AI.

• Decommissioning and cleanup of nuclear power plants, specifically for managing radioactive graphite moderators.
• Waste treatment facilities handling radioactive carbon waste.
• Chemical industry systems reusing the separated non-radioactive carbon monoxide for industrial processes.
• Facilities aiming to reduce long-term radioactive waste storage needs.
• Research laboratories seeking safe methods for isotope separation and radioactive material handling.

BenefitsContent extracted from patent full text and abstract with AI.

• Significantly reduces the quantity of radioactive waste requiring long-term storage, lowering costs and environmental impact.
• Allows recycling and potential industrial reuse of non-radioactive material, such as CO for chemical synthesis.
• Improves safety by removing and relaxing stored energy (Wigner energy) within graphite moderators, reducing risks during disposal.
• Enables isolation of radioactive carbon isotopes for potential further use or safe containment, enhancing radioactive management.
• Offers a scalable, systematic approach to treating large volumes of radioactive graphite, supporting efficient nuclear plant decommissioning.

Technical Classifications (CPCs)

Inventors & Applicants

Patent Abstract

The invention relates to a method and system for disposing and/or recycling of a radioactive contaminated component of a nuclear power plant, in particular a radioactive contaminated graphite moderator, comprising the following steps : - a thermal treatment step (II) wherein the radioactive contaminated component is thermally treated at a temperature at which a gas mixture (2a) containing carbon monoxide is formed, - at least one subsequent separation step (V) wherein the gas mixture (2a, 2b) is supplied to a separating device (16) for separating components present in the gas mixture (2a, 2b), in particular for separating radioactive carbon monoxide 14CO and non-reactive carbon monoxide 12CO, from each other.