Nuclear Reactor Vessel Support System with External Steam Generators
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Solution Overview
Problem
Existing nuclear reactor systems with natural circulation of primary coolant face challenges such as integrated heat exchange equipment within the reactor pressure vessel, making maintenance difficult and increasing the risk of pipe failures due to complex piping and numerous joints.
Innovation Solution
A nuclear reactor system design that utilizes natural circulation to circulate a primary coolant in a single-phase through a reactor core with a heat exchange sub-system located outside the reactor pressure vessel, minimizing pressure drop and eliminating penetrations in the reactor vessel's below-ground portion, thus enhancing safety and accessibility.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Temperature
If heat exchange equipment is integrated within the reactor pressure vessel, then heat transfer efficiency is improved, but maintenance difficulty increases and device complexity increases
Solution Approach 1:
The heat exchange system is segmented into separate components: the reactor pressure vessel contains only the reactor core, while the steam generators are separate external components. This segmentation allows the steam generators to be maintained and serviced independently without disassembling the reactor pressure vessel, resolving the contradiction between integrated heat transfer efficiency and maintenance accessibility.
Solution Approach 2:
The steam generators are extracted from the reactor pressure vessel and positioned externally. This extraction eliminates the need for complex internal piping and multiple penetrations in the reactor pressure vessel, reducing device complexity while maintaining effective heat transfer through the external steam generator components.
2Temperature
If multiple penetrations and piping joints are used to connect heat exchange equipment, then heat transfer capability is improved, but reliability decreases due to increased pipe failure risk
Solution Approach 1:
The steam generators are extracted from the reactor pressure vessel, eliminating the need for multiple penetrations and internal piping joints. This reduces the number of potential failure points while maintaining effective heat transfer through the external steam generator components that connect via fewer, more reliable interfaces.
Solution Approach 2:
The system is segmented into distinct functional zones: the reactor pressure vessel with the reactor core, and separate external steam generators. This segmentation reduces the complexity of piping connections and eliminates multiple penetrations in the reactor pressure vessel, thereby improving reliability while preserving heat transfer capability.
3Adaptability or versatility
If active components and complex piping are used, then operational flexibility is improved, but device complexity increases and safety risks increase
Solution Approach 1:
The steam generators are extracted from the reactor pressure vessel, simplifying the piping architecture to only external connections. This reduces device complexity while maintaining operational flexibility through the natural circulation system that requires no active components within the reactor pressure vessel.
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 design simplifies maintenance, reduces the risk of pipe failures, and ensures inherent safety by eliminating the need for active components, off-site power, and minimizing the potential for large break LOCA events, while maintaining efficient heat transfer and operational reliability.
Implementation Method 1
a reactor core with a heat exchange sub-system located outside the reactor pressure vessel... operation of the reactor core causes natural circulation of the primary coolant
Implementation Method 2
the primary coolant circulation is achieved by natural circulation... the hot primary coolant moves from the core through the riser and upper shroud windows
Implementation Method 3
utilize the phenomenon of natural circulation (also known as thermosiphon effect) to circulate the primary coolant
Implementation Method 4
decreasing its enthalpy by giving up heat to the secondary coolant in the steam generator... vaporize a secondary coolant into motive vapor
Implementation Method 5
vaporize a secondary coolant into motive vapor
Implementation Method 6
the primary coolant exits the internal steam generators and flows down through the down-comer to the lower plenum, closing the circuit
Data Source
AI summary
A nuclear reactor support system that, in one embodiment, includes a reactor vessel, a reactor core disposed within the reactor vessel, an upper portion of the reactor vessel located above a ground plane and a lower portion of the reactor vessel located below the ground plane. The support system further includes a first flange fixedly attached to the upper portion of the reactor vessel and contacting the ground plane, the first flange supporting the reactor vessel, a second flange fixedly attached to the upper portion of the reactor vessel above the ground plane, the second flange spaced vertically apart from the first flange, and a plurality of welded lugs extending vertically between the first and second flanges. The first flange supports the entire weight of the reactor vessel in a cantilevered manner.