Transportable Low-Enriched Nuclear Energy Source With Removable Core
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Solution Overview
Problem
Existing nuclear reactor designs lack a unified power series and safe refueling mechanism, particularly for compact, transportable reactors using low-enriched nuclear fuel.
Innovation Solution
A compact transportable pressure vessel with a core containing low-enriched nuclear fuel, utilizing boric acid as a continuously agitated heat-exchange liquid for cooling and neutron shielding, and a dual-pressure vessel system for heat transfer and steam production, ensuring safe operation and transport.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Ease of operation
If a compact transportable pressure vessel with low-enriched nuclear fuel is used, then the reactor becomes more transportable and safer for handling, but the refueling process becomes more complex requiring a dedicated workplace
Solution Approach 1:
The reactor core is designed as a separate, removable heating element (TT) that can be independently handled and transported. The core is segmented from the pressure vessel, allowing it to be replaced at a dedicated workplace without moving the entire reactor system, thus simplifying refueling operations while maintaining transportability.
Solution Approach 2:
A dedicated refueling workplace serves as an intermediary facility between the transportable reactor and the fuel supply system. This specialized location handles the complex refueling operations, allowing the reactor itself to remain simple and transportable while delegating complex tasks to a dedicated infrastructure.
2Reliability
If boric acid is used as continuously agitated heat-exchange liquid, then cooling efficiency and neutron shielding are improved, but the system complexity increases
Solution Approach 1:
The boric acid heat-exchange liquid performs multiple functions simultaneously: it provides continuous cooling of the reactor core, acts as a neutron shield, and serves as a cooling agent for the pressure vessel. This multi-functionality improves reliability while avoiding the need for separate systems for each function.
Solution Approach 2:
The heat-exchange liquid circulates continuously through the system, automatically absorbing heat from the core and providing neutron shielding without requiring external intervention. The system self-regulates temperature and radiation protection through the continuous circulation and chemical properties of the boric acid solution.
3Reliability
If double separation of radioactive fuel from utility steam is implemented, then safety is improved, but the system complexity and manufacturing cost increase
Solution Approach 1:
The system uses two separate pressure vessels: one containing the radioactive fuel and boric acid heat-exchange liquid, and another containing the utility steam generation system. This segmentation physically separates the radioactive and non-radiovasive zones, enabling double separation while maintaining a relatively simple overall structure through modular design.
Solution Approach 2:
The steel wall of the first pressure vessel acts as an intermediary barrier between the radioactive fuel and the utility steam system. Heat is transferred through this barrier, allowing thermal energy transfer while maintaining physical and radiological separation between the fuel and steam, thus improving safety without requiring complex direct contact systems.
4Manufacturing precision
If the core is designed with exclusive fuel supplier competence, then manufacturing precision and safety are improved, but the device complexity increases
Solution Approach 1:
The core design is optimized with specific local qualities tailored to the low-enriched nuclear fuel and boric acid heat-exchange system. The heating element geometry, fuel arrangement, and cooling channels are locally optimized for this specific configuration, improving manufacturing precision while the modular nature limits overall system complexity.
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
Enables unified power series manufacturing and safe handling of low-enriched nuclear fuel reactors, providing double separation of radioactive fuel and stable energy production.
Implementation Method 1
a continuously agitated heat-exchange liquid, which may be in the form of boric acid. The internal flow of the liquid is directed and thus ensures the cooling of the cylinder
Implementation Method 2
continuously agitated heat-exchange liquid... The internal flow of the liquid is directed and thus ensures the cooling
Implementation Method 3
serves as a shield against free neutrons and prevents accelerated degradation of the material of the pressure vessel
Implementation Method 4
the heat created by the nuclear core fission process is transferred through the steel wall
Implementation Method 5
the heat created by the nuclear core fission process is transferred through the steel wall to the other pressure vessel
Implementation Method 6
where the water heated by the described process if forced into the heat exchanger, where the heat transferred in this way is used in the standard way to produce steam
Data Source
AI summary
An energy source using low-enriched nuclear fuel to produce heat contains a compact transportable pressure vessel containing a cylinder with the core with heating element formed by nuclear fuel and continually agitated by a directed flow of heat-exchange liquid, to which a second pressure vessel is connected with a closed water bath circuit and a heat exchanger for production of steam, while the compact transportable pressure vessel can be placed in a space selected from the group underground concrete space with stainless steel lining, sea-river vessel and container modification for road and/or railway transport.