Comsol > 实例探究 > Researching a New Fuel for the HFIR: Advancements at ORNL Require Multiphysics Simulation to Support Safety and Reliability

Researching a New Fuel for the HFIR: Advancements at ORNL Require Multiphysics Simulation to Support Safety and Reliability

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公司规模
Large Corporate
地区
  • America
国家
  • United States
产品
  • COMSOL Multiphysics
技术栈
  • Multiphysics Simulation
  • Fluid-Structure Interaction (FSI)
  • Computational Fluid Dynamics (CFD)
实施规模
  • Enterprise-wide Deployment
影响指标
  • Productivity Improvements
  • Innovation Output
技术
  • 分析与建模 - 预测分析
  • 分析与建模 - 实时分析
  • 应用基础设施与中间件 - 数据可视化
适用行业
  • 国家安全与国防
  • 医疗保健和医院
适用功能
  • 产品研发
  • 质量保证
用例
  • 预测性维护
  • 过程控制与优化
  • 远程资产管理
服务
  • 软件设计与工程服务
  • 系统集成
  • 测试与认证
关于客户
Oak Ridge National Laboratory (ORNL) is a multi-disciplinary research facility located in Oak Ridge, Tennessee, USA. It is managed by UT-Battelle for the U.S. Department of Energy. ORNL is known for its cutting-edge research in various fields, including nuclear science, materials science, and energy production. The High Flux Isotope Reactor (HFIR) at ORNL is a key facility that provides neutron scattering capabilities, stable and radio isotopes, and unique irradiation experiment facilities. The HFIR is used by over 500 researchers from around the world each year and is one of the highest steady-state neutron flux reactors globally. ORNL's mission includes advancing scientific knowledge, supporting national security, and contributing to technological innovation. The laboratory collaborates with academia, industry, and government agencies to achieve its research and development goals.
挑战
The High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) is undergoing a conversion from highly enriched uranium (HEU) to low-enriched uranium (LEU) fuel to meet the Global Threat Reduction Initiative's requirements. This conversion presents a complex challenge due to the unique fuel and core design of the HFIR, as well as its high power density. The primary challenge is to ensure that the new LEU fuel can maintain the reactor's performance, safety, and reliability. Researchers need to evaluate the impact of the fuel change on various aspects such as neutron scattering, isotope production, irradiation experiments, and neutron activation analyses. Additionally, the HFIR will need to operate at a higher power level (100 MW) to maintain the same neutron flux, which increases the demands on the reactor's thermal margin and safety.
解决方案
Researchers at ORNL are using COMSOL Multiphysics® simulation software to explore the impact of converting the HFIR from HEU to LEU fuel. The new fuel design involves reducing the uranium-235 enrichment from 93% to 19.75%. To accommodate changes in nuclear characteristics, density, and thermal properties, the HFIR core fuel meat must be redesigned. Preliminary studies indicate that the HFIR will need to operate at 100 MW to maintain the same neutron flux, increasing thermal demands. The COMSOL Multiphysics software is used to conduct fluid-structure interaction (FSI) simulations to evaluate the safety and performance of the new fuel design. These simulations help predict fuel plate deflections and ensure that the reactor can maintain the required coolant flow rate. Validation studies are conducted to prove the accuracy of the COMSOL code, ensuring that the models are reliable and meet safety standards. The fully-coupled FSI approach in COMSOL has shown excellent agreement with experimental results, providing confidence in the new fuel design.
运营影响
  • The use of COMSOL Multiphysics has enabled ORNL researchers to accurately predict the fluid-structure interactions and deflections of the HFIR fuel plates.
  • The fully-coupled FSI approach has improved the stability and accuracy of the simulations, ensuring reliable results.
  • The validation studies have confirmed the accuracy of the COMSOL code, providing confidence in the safety and performance of the new LEU fuel design.
  • The simulations have helped identify the necessary design changes to accommodate the new fuel while maintaining the reactor's performance and safety.
  • The ongoing development of the HFIR model using LEU fuel is expected to contribute to a safety basis case for the ultimate fuel conversion.
数量效益
  • The HFIR will need to operate at 100 MW instead of 85 MW to maintain the same neutron flux.
  • The uranium-235 enrichment will be reduced from 93% to 19.75%.

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