Subcritical Nuclear Modules in Intermodal Containers
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Solution Overview
Problem
Current nuclear power generators face challenges in safely managing decay heat after shutdown, relying on complex external systems that require electric power and are vulnerable to failures, especially in extreme conditions, and have issues with hydrogen production and transportation weight limitations for modular reactors.
Innovation Solution
A transportable, modular nuclear reactor system that is inherently sub-critical, using environmental air for cooling, and can be assembled to form a critical system, with sealed sub-critical modules that do not require on-site power connections, can withstand hostile attacks, and can operate remotely, providing a lightweight, efficient, and safe power generation solution.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Reliability
If active safety systems with electrically driven re-circulators are used to remove decay heat, then decay heat removal capability is improved, but dependence on electric power and system complexity increase
Solution Approach 1:
The reactor core is designed with passive safety features where natural circulation of coolant occurs without electrically driven pumps. The system uses gravity and density differences to drive coolant flow through the core, eliminating dependence on external electric power sources for decay heat removal.
Solution Approach 2:
The invention removes electrically driven re-circulators and complex control systems from the decay heat removal mechanism, extracting only the essential natural circulation capability that relies on fundamental physical principles rather than active mechanical components.
2Reliability
If passive safety features with large coolant inventories stored at high elevations are used, then decay heat removal is improved, but weight and environmental dependency increase
Solution Approach 1:
The coolant system is designed with localized cooling channels directly integrated into the reactor core structure. Instead of storing large quantities of coolant at high elevations, the system uses strategically placed cooling paths that efficiently remove heat at the source with minimal coolant inventory.
Solution Approach 2:
The invention transitions from vertical elevation-based passive cooling (requiring high coolant storage positions) to a distributed three-dimensional cooling network within the core structure, utilizing horizontal and radial heat transfer paths that eliminate the need for gravitational head.
3Adaptability or versatility
If modular reactor design is used for transportability, then deployment flexibility is improved, but weight limitations for transportation are worsened
Solution Approach 1:
The reactor system is divided into modular components that can be transported separately and assembled on-site. This segmentation allows each module to meet transportation weight limits while the complete assembled system achieves the required power generation capability and safety features.
Solution Approach 2:
Multiple lightweight modular units are combined to form a complete reactor system. The merging of modules creates a critical mass for sustained operation while each individual module remains transportable by conventional means, resolving the contradiction between modularity and weight.
4Reliability
If redundant external piping and heat exchangers are used for decay heat removal, then safety is improved, but infrastructure requirements and vulnerability to attacks increase
Solution Approach 1:
The cooling function is integrated directly into the reactor core structure, merging the fuel elements, cooling channels, and heat transfer mechanisms into a single unified assembly. This eliminates external piping and separate heat exchangers, reducing infrastructure that could be targeted or damaged.
Solution Approach 2:
The reactor core structure serves multiple functions simultaneously: fuel containment, heat generation, coolant flow path provision, and heat rejection. This multi-functionality eliminates the need for dedicated separate safety systems with external piping, reducing overall system vulnerability.
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
The system enables rapid deployment and load-following capabilities, operates independently of electric grids, and provides reliable power generation with reduced infrastructure needs, enhanced safety features, and compliance with zero-evacuation planning zones, while minimizing weight and environmental impact.
Implementation Method 1
Nuclear cores that naturally produce decay thermal energy after shutdown
Implementation Method 2
transfer thermal energy from the core to the environment
Implementation Method 3
the coolant may be passively circulated through the core by gravity-driven natural circulation mechanisms based on coolant density changes
Implementation Method 4
power conversion and conditioning for remote electric generation via combined Brayton and Rankine power cycles
Implementation Method 5
power conversion and conditioning for remote electric generation via combined Brayton and Rankine power cycles
Data Source
AI summary
A transportable nuclear power system is provided. The system includes a nuclear power generator. The nuclear power generator includes one or more fuel cartridges configured to form a critical core during a power generation operation, each of the one or more fuel cartridges containing a nuclear fuel. The nuclear power generator also includes a reactivity controller and one or more working fluid conduits, each work fluid conduit containing a working fluid circulating within each of the one or more fuel cartridges to cool the nuclear fuel and execute a thermodynamic cycle. The system also includes an intermodal transport container including a support structure mounted inside the intermodal transport container to support at least the one or more fuel cartridges of the nuclear power generator. The one or more fuel cartridges of the nuclear power generator are contained in the intermodal transport container during the power generation operation.