SRNL'S LESSONS LEARNED FROM THE UNIVERSITY OF NEVADA RENO NUCLEAR PACKAGING INTERNSHIPS
Explore the source record for details and available documents.
SEARCH · Engineering Papers
Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.
Explore the source record for details and available documents.
Explore the source record for details and available documents.
Abstract not provided.
Abstract not provided.
Several Nuclear Power Plants (NPPs) in USA are facing premature closures due to financial difficulties. A significant contributing factor in the NPP electricity generation cost is Operational and Maintenance (O&M) cost. This research aims to reduce O&M cost by developing a framework which creates flexibility in NPP maintenance program. This framework relies on FLEX portable equipment to reduce NPP risk and to substitute and/or backup fixed equipment in different NPP operation modes. Probabilistic Risk Assessment (PRA) methodology is used to quantify the change of plant risk to justify the framework's applicability. The framework enables plant managers to shift maintenance workload from refueling outage period into online maintenance programs. As a result, it is expected to increase NPP capacity factor while also reducing the risk of unexpected outage. These results are expected to increase NPP electricity generation revenue and decrease O&M costs while complying to existing nuclear safety regulations.
These deliverables present a design for a new orifice flow meter to be installed in three experiment loops at the Advanced Test Reactor. The current configuration of the experiment loop system has an orifice that is not properly sized to the low flow rates of the degas line of the pressurizer system, causing inaccurate flow measurements. Under consideration of flow conditions and system constraints, an iterative procedure was utilized to determine the optimal sizing for a new orifice. This orifice is designed to accurately and precisely measure the flow rate of the degas line, which will consequently improve control of the pressure and chemistry of the loop pressurizer system. The scope of this project includes recommendations for orifice sizing, material, flange type, face type, and installation location on the loop piping spools. The design is suitable for experiment loops 1D-N, 2B-SE, and 2D-SW and meets all necessary standards.
This study covers leveraging reactor testing facilities that are primarily designed with a focus on safety to enhance cybersecurity testing. By incorporating reactor security-by-design with reactor safety-by-design principles and adopting defense-in-depth strategies that emphasize both safety and security, the research evaluates applicable cyber tools, models, and solutions. This includes simulating specific cyber-attack scenarios using reactor simulators and performing SWOT (Strengths, Weaknesses, Opportunities, Threats) analysis to improve the cybersecurity of reactor systems.