Session: 11-10-01: Multiphase Flow Applications
Paper Number: 166265
Performance Analysis and Simulation of the Hydraulic SCRAM System in TREAT Reactor
The Transient Reactor Test (TREAT) Facility plays a crucial role in nuclear fuel safety research, particularly in studying fuel behavior under extreme conditions. As nuclear energy remains a key component of the global energy portfolio, ensuring the safety and reliability of reactor operations is of great importance. TREAT is designed to conduct transient experiments that simulate rapid power changes and accident situations, providing valuable data on fuel performance, failure mechanisms, and safety margins. A critical aspect of TREAT’s operation is its reactor scram system, which ensures the rapid and reliable shutdown of the reactor during transient experiments. This system prevents fuel damage, mitigates risks, and enhances overall reactor safety. This project focuses on the hydraulic scram mechanism, investigating its performance, reliability, and potential enhancements to improve reactor safety and operational efficiency. The hydraulic scram system is responsible for inserting control rods into the reactor core at high speeds to halt the fission reaction in emergency scenarios. Given the importance of this function, it is essential to thoroughly analyze its response time, pressure dynamics, and fluid flow characteristics to identify opportunities for improvement. The study will employ a combination of experimental testing and computational modeling to evaluate the scram system's dynamics. Experimental testing will involve measuring key parameters such as pressure variations, flow rates, and actuation times under different operating conditions. This data will provide insight into the factors that influence system performance and potential areas for refinement. Additionally, computational fluid dynamics (CFD) and finite element analysis (FEA) will be utilized to simulate the hydraulic behavior of the scram mechanism, offering a detailed understanding of how the system operates under various scenarios. A key focus of the study will be the damping rate of the hydraulic scram mechanism, which plays a crucial role in system stability and shutdown performance. Excessive damping may slow down the scram response, while insufficient damping could lead to mechanical stresses or system instability. By characterizing the damping behavior, researchers can optimize the system to ensure rapid yet controlled shutdowns. Furthermore, failure mode analysis will be conducted to identify potential vulnerabilities in the scram system. This will involve evaluating previous data, conducting mechanical tests, and assessing component wear and degradation over time. By understanding potential failure points, recommendations can be made to enhance system robustness, improve reliability, and extend operational lifespan. These findings will contribute to TREAT’s continued role as a premier transient testing facility by ensuring its scram system operates with high precision and reliability. The outcomes of this study will support advancements in nuclear safety protocols, benefiting future reactor development and accident mitigation strategies. By improving the performance and resilience of the hydraulic scram mechanism, this research will help maintain the integrity of transient testing operations and contribute to the broader goal of nuclear safety and sustainability.
Presenting Author: Dominic Mandato Kennesaw State University
Presenting Author Biography: Dominic is pursuing a Master’s degree in Mechanical Engineering, focusing on hydraulic systems through his Master’s Project with Idaho National Laboratory’s TREAT reactor. He earned his undergraduate degree in Mechanical Engineering Technology from KSU in Fall 2024. As a Graduate Teaching Assistant in the Engineering Technology Department, Dominic supports courses in Engineering Materials, Rapid Design/Prototyping, and Senior Design Labs.
Authors:
Dominic Mandato Kennesaw State UniversityAaron Adams Kennesaw State University
David Start Idaho National Laboratory
Brandon Moon Idaho National Laboratory
Doug Crawford Idaho National Laboratory
Performance Analysis and Simulation of the Hydraulic SCRAM System in TREAT Reactor
Paper Type
Technical Paper Publication