基于降阶模型的热管堆核热力耦合启堆瞬态模拟研究

沈书秋; 熊进标; 刘晓晶; 张滕飞

doi:10.11889/j.0253-3219.2025.hjs.48.240471

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基于降阶模型的热管堆核热力耦合启堆瞬态模拟研究

第二十七届中国科协年会学术论文专题 | 更新时间：2025-06-16

- 基于降阶模型的热管堆核热力耦合启堆瞬态模拟研究
- Transient simulation of nuclear thermal-hydraulic coupling startup of heat pipe reactor based on reduced-order models
- 核技术 2025年48卷第6期文章编号：060013
- 作者机构：
  
  1.上海交通大学核科学与工程学院上海 200240
  2.上海交通大学智慧能源与创新学院上海 200240
  3.上海市数值反应堆技术融合创新中心上海 200240
- 作者简介：
  
  沈书秋，男，1999年出生，2022年毕业于上海交通大学，现为硕士研究生，研究领域为反应堆物理数值计算
  张滕飞，E-mail：zhangtengfei@sjtu.edu.cn
- 基金信息：
  
  国家自然科学基金(12175138);上海市青年科技启明星计划(23QA1405500);中核集团领创科研项目(CNNC-LC-2020)
- DOI：10.11889/j.0253-3219.2025.hjs.48.240471
  中图分类号： TL328
- 收稿日期：2024-11-22，
  
  修回日期：2025-02-12，
  
  纸质出版日期：2025-06-15
- 稿件说明：
移动端阅览
沈书秋,熊进标,刘晓晶等.基于降阶模型的热管堆核热力耦合启堆瞬态模拟研究[J].核技术,2025,48(06):060013.

SHEN Shuqiu,XIONG Jinbiao,LIU Xiaojing,et al.Transient simulation of nuclear thermal-hydraulic coupling startup of heat pipe reactor based on reduced-order models[J].NUCLEAR TECHNIQUES,2025,48(06):060013.
沈书秋,熊进标,刘晓晶等.基于降阶模型的热管堆核热力耦合启堆瞬态模拟研究[J].核技术,2025,48(06):060013. DOI： 10.11889/j.0253-3219.2025.hjs.48.240471. CSTR： 32193.14.hjs.CN31-1342/TL.2025.48.240471.

SHEN Shuqiu,XIONG Jinbiao,LIU Xiaojing,et al.Transient simulation of nuclear thermal-hydraulic coupling startup of heat pipe reactor based on reduced-order models[J].NUCLEAR TECHNIQUES,2025,48(06):060013. DOI： 10.11889/j.0253-3219.2025.hjs.48.240471. CSTR： 32193.14.hjs.CN31-1342/TL.2025.48.240471.

摘要

MegaPower是一种设计用于偏远地区和军事基地等去中心化能源市场的热管冷却反应堆，其启堆过程涉及复杂的多物理场耦合计算。传统高分辨率仿真方法常面临较高的计算成本。本研究以MegaPower热管堆的启堆过程为研究对象，提出了一种基于Proper Orthogonal Decomposition-Radial Basis Function（POD-RBF）快速预测方法的核热力耦合模型，以实现复杂瞬态工况的高效模拟。通过构建MegaPower高分辨率1/6堆芯模型，并结合OpenMC、FEniCSx和POD-RBF快速预测模型对堆芯的多物理场行为进行模拟，研究了启堆阶段的功率、温度和反应性动态特性。模拟结果表明，POD-RBF方法能够准确稳定地预测堆芯功率分布，最大误差为3.04%，平均误差为0.77%；

eff

预测的平均误差低于50 pcm（percent mille），最大误差不超过100 pcm。在启堆功率调节阶段，功率上升速率约为每秒0.53%额定功率，最终平稳达到额定功率，功率与反应性的动态变化保持稳定。同时，POD-RBF方法显著提升了计算效率，将单个时间步计算时间从传统高分辨率模型的800 s降低至3 s，整个启堆过程模拟时间由74 d缩短至7.5 h，效率提升约99.6%。研究结果表明，基于POD-RBF方法的热管堆核热力耦合模型能够显著提高计算效率，同时在瞬态问题中具备较高的预测精度，为热管堆的设计优化与安全评估提供了参考，也为多物理场问题的快速仿真提供了新思路。

Abstract

Background

MegaPower is a heat pipe reactor designed for decentralized energy markets

such as remote areas and military bases. Its startup process involves complex multi-physics coupling calculations. Traditional high-resolution simulations often face high computational costs.

Purpose

This study aims to develop and validate a fast reduced-order model based on the Proper Orthogonal Decomposition-Radial Basis Function (POD-RBF) method to efficiently simulate the startup process of the MegaPower heat pipe reactor.

Methods

Firstly

a high-resolution 1/6 core model was constructed to capture the essential features of MegaPower

and OpenMC was employed to model the 1/6 core model

maintaining the symmetry and main structural characteristics of the reactor geometrically. Then the neutron transport calculations were carried out by using OpenMC

and FEniCSx was used for thermal-hydraulic and stress analysis. Subsequently

the POD-RBF method was integrated into the model to reduce computational cost while maintaining accuracy. Finally

the dynamic behavior of power

temperature

and reactivity during the startup process was analyzed and compared against high-resolution simulation results.

Results

The simulation results indicate that the POD-RBF method achieves accurate predictions with an average power distribution error of 0.77% and a maximum error of 3.04%

and the entire startup process simulation time is reduced from 74 d to just 7.5 h

achieving an efficiency improvement of approximately 99.6%. Reactivity prediction results show that an average error below 50 pcm and a maximum error not exceeding 100 pcm are achieved. The power ramp rate during the adjustment phase reaches approximately 0.53% FP/s

with the reactor achieving nominal power smoothly and maintaining stable power and reactivity dynamics. Furthermore

the POD-RBF method significantly enhances computational efficiency

reducing the time per time step from 800 s to 3 s.

Conclusions

The results of this study verify the efficiency and accuracy of the POD-RBF method for simulating transient multi-physics coupling problems

providing reliable computational support for the design and safety assessment of heat pipe reactors and offers a new methodology for addressing complex multi-physics problems efficiently.

关键词

Keywords

references

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