Dual-Vessel Nuclear Reactor for Radionuclide Transmutation
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Solution Overview
Problem
The challenge of securing safe burial disposal for high-level radioactive waste generated by nuclear reactors due to the difficulty in managing long-life radioactive nuclides and short-life radioisotopes, which poses environmental risks.
Innovation Solution
A nuclear reactor system designed with two regions, one for fast neutrons and one for thermal neutrons, utilizing a dual-vessel structure to accelerate the decay of radionuclides through neutron capture and low-frequency electromagnetic fields, facilitating the transmutation of long-life radioactive elements into stable nuclides and shortening the half-life of short-lived isotopes.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Productivity
If conventional nuclear reactors generate electricity using standard fuel cycles, then energy production is achieved, but long-life radioactive nuclides accumulate requiring secure burial disposal
Solution Approach 1:
The patent converts the harmful long-life radioactive nuclides into beneficial stable nuclides through neutron transmutation. The reactor system uses neutron irradiation to transform radioactive waste materials (such as minor actinides and long-life fission products) into stable or short-life nuclides, thereby eliminating the need for secure burial disposal while maintaining electricity generation
Solution Approach 2:
The patent changes the neutron energy spectrum parameter by incorporating both fast neutron and thermal neutron regions. This dual-spectrum approach optimizes transmutation efficiency for different types of radioactive nuclides, enabling effective conversion of long-life radioactive materials into stable forms while generating power
2Productivity
If fast neutrons are used for transmutation, then transmutation efficiency is improved, but neutron flux distribution becomes difficult to control
Solution Approach 1:
The patent segments the reactor core into distinct fast neutron and thermal neutron regions. This segmentation allows independent optimization of neutron flux characteristics in each zone, with the fast region providing high transmutation efficiency and the thermal region providing controllable neutron population through moderation
Solution Approach 2:
The patent introduces a neutron moderator as an intermediary between the fast neutron source and the transmutation targets. The moderator (such as water or graphite) slows down neutrons from the fast region to create a thermal neutron region, enabling controlled neutron flux distribution and improved overall transmutation effectiveness
Applied Scientific Principles
This section explains which scientific principles are used to turn an abstract innovation direction into a practical engineering solution.
Function Achieved in This Case
This approach enables the generation of electricity while effectively reducing the radioactivity of nuclear waste by promoting the transmutation of long-life nuclides into stable forms and accelerating the decay of short-life isotopes, thereby enhancing safety and reducing waste management challenges.
Implementation Method 1
promoting nuclear transmutation of long-life radioactive nuclides, such as radioactive nuclear fission products, into stable nuclides
Implementation Method 2
accelerating decay processes of relatively short-life radioisotope nuclides by use of application of low-frequency magnetic field
Implementation Method 3
transferring thermal energy generated by the fast neutrons to a heat exchanger by use of the primary coolant
Data Source
AI summary
Provided is a nuclear reactor system and method therefor, for increasing the speed of conversion of a radionuclide to a stable nuclide to reduce radionuclide concentration using thermal neutrons produced by reducing the velocity of fast neutrons, while simultaneously subjecting fast-neutron-induced thermal energy of a primary cooling material to heat exchange with a secondary cooling material in a heat exchanger (7), and feeding the energy to a turbine system to generate power, the system having a nuclear reactor container (1) comprising a first container (11), and a second container (12), a plurality of metal fuel assemblies (22) and a liquid metal, which is the primary cooling material, being disposed in the first container, and the second cooling material capable of dual use as a neutron moderator and a MA radioactivity-extinguishing assembly or FP-extinguishing assembly (24) being loaded in the second container.