The Practical Pin-by-Pin Two-Step Method is an innovative approach designed to streamline reactor core analysis. This Method combines The strengths of detailed transport calculations and simplified diffusion theory to provide accurate results with reduced computational effort. The first Step involves using high-fidelity transport calculations to generate group constants, which are then employed in The second Step within a simplified diffusion framework to analyze The reactor core on a Pin-by-Pin basis.
This Pin-by-Pin approach ensures that The detailed physics captured in The transport calculations are effectively utilized in The more computationally efficient diffusion calculations. The Practical Pin-by-Pin Two-Step Method is especially valuable in routine reactor operation analyses, fuel management, and safety assessments, where both accuracy and efficiency are paramount.

Nodal/CMFD Method based on Diffusion Theory

Nodal Method

The Nodal Method is a highly efficient and accurate approach for solving neutron transport problems. This method divides the reactor into nodes, treating each node independently and connecting them through boundary conditions to predict the overall neutron distribution within the reactor. Particularly, the Nodal Method excels in reducing computational costs by transforming high-dimensional problems into lower-dimensional ones, making it a powerful tool for reactor analysis and design.

CMFD Method

The Coarse Mesh Finite Difference (CMFD) method enhances the Nodal Method by further reducing computational requirements while maintaining accuracy. CMFD simplifies the neutron diffusion equation over larger mesh sizes, allowing for faster computations without significant loss of detail. This approach is particularly useful in large-scale reactor simulations where computational efficiency is crucial.

Montecarlo Method based on Transport Theory

The Monte Carlo Method, grounded in Transport Theory, is a statistical technique used to model neutron behavior with high precision. This method simulates individual neutron paths, accounting for various interactions such as scattering and absorption. By tracking a large number of neutrons, the Monte Carlo Method provides detailed insights into neutron transport phenomena, offering a robust solution for complex reactor geometries and heterogeneous materials.
The strength of the Monte Carlo Method lies in its ability to handle intricate geometries and boundary conditions, making it an indispensable tool for reactor physics, radiation shielding, and dosimetry. Despite its computational intensity, advancements in computing power and algorithms continue to enhance its practicality and accuracy.

Innovative SMR Design

Small Modular Reactors (SMRs) represent a cutting-edge approach to nuclear power generation, offering flexibility, scalability, and enhanced safety features. Our research includes the development of innovative reactor core designs, advanced materials, and state-of-the-art control systems to enhance the performance and reliability of SMRs.

Practical Commercial Nuclear Design

Our research in Practical Commercial Nuclear Design focuses on the optimization and enhancement of existing commercial nuclear power plants. This includes improving reactor efficiency, extending plant life, and ensuring the highest standards of safety and reliability.