A method for determining a flow blocking measurement point and a flow blocking assembly of a lead-based reactor core

By constructing core thermal analysis tools and CFD models, the thermal characteristics of the lead-based reactor core and outlet chamber were optimized, solving the problem of choke monitoring and achieving safe and stable operation of the lead-based reactor and accurate positioning of choke components.

CN122158209APending Publication Date: 2026-06-05NUCLEAR POWER INSTITUTE OF CHINA
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Patent Information

Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
NUCLEAR POWER INSTITUTE OF CHINA
Filing Date
2025-12-01
Publication Date
2026-06-05

AI Technical Summary

Technical Problem

In low-flow-rate and low-temperature regions, lead-based reactors are prone to the precipitation, deposition, and accumulation of chemical substances, which can lead to partial or complete blockage of coolant channels, affecting flow and heat transfer characteristics. Furthermore, it is difficult to arrange traditional core outlet temperature measurement points for every component, which limits the ability to monitor blockage.

Method used

A core thermal analysis tool was developed, which combined computational fluid dynamics programs and turbulent heat transfer models to optimize the analysis of the thermal characteristics of the core and the outlet chamber, determine the location of choking measurement points and components, and construct a core-chamber coupling analysis tool by using CFD dominant-subchannel correction or region separation methods to reduce the number of measurement points and identify choking components.

Benefits of technology

This effectively reduces the number of core clogging measurement points, ensures the safe and stable operation of the reactor, and allows for timely identification of clogging component locations, preventing damage to fuel cladding heat transfer and radioactive release.

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Abstract

The present application belongs to the technical field of lead-based reactors, and particularly relates to a method for determining a flow blocking measuring point and a flow blocking assembly of a lead-based reactor core. The present application comprises the following steps: Step 1, obtaining a database required for model construction and program verification; Step 2, obtaining a database required for model optimization and program verification; Step 3, constructing a core-chamber coupling analysis tool for analyzing the thermal characteristics of the reactor after flow blocking; Step 4, based on the core-chamber coupling analysis tool, analyzing the cladding temperature after flow blocking of the core and the temperature field of the core outlet chamber; Step 5, based on the changes of the cladding temperature and the outlet chamber temperature field before and after flow blocking, determining a core outlet temperature measuring point arrangement scheme; Step 6, based on the temperature change of the flow blocking measuring point, determining the position of the core flow blocking assembly. The present application can help to reduce the number of core flow blocking measuring points on one hand, and effectively identify the position of the core flow blocking assembly on the other hand, which helps to ensure the long-term safe and stable operation of the reactor.
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