ML24155A005
| ML24155A005 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/2024 |
| From: | Gascot-Lozada R NRC/RES/DE/RGDB |
| To: | |
| References | |
| Download: ML24155A005 (1) | |
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Light Water Reactor Sustainability (LWRS) is a Department of Energy (DOE) program conducting research to develop technologies and other solutions to improve the economics and reliability, sustain the safety, and extend the operation of our nation's fleet of nuclear power plants (NPP). The NRC and the DOE has a Memorandum of Understanding (MOU) on Nuclear Innovation that allow the entities to share expertise and knowledge on advanced nuclear reactor technologies and nuclear energy innovation which extend to the area of light water reactor long-term operation and proposed modification for light water reactor sustainability.
LWRS Status Highlights Main Goal: enable plant efficiency improvements through a strategy for long-term modernization Latest Report :
Development of Human and Technology Integration Guidance for Work Optimization and Effective Use of Information-This report describes the development of an extension of the human and technology integration methodology, herein referred to as the Human Integration and Technology Task Force for Work Management Optimization (HITT), to support the safe, reliable, and efficient use of proposed innovations with the intended users in their intended environment to perform their intended tasks. The intent of this work is to provide practical guidance for industry to follow to ensure that the proposed digital technologies are implemented in a way that are usable to the intended users in the intended environment.
May 2024 Plant Modernization Pathway Program Mission Key benefits of the HITT process
Risk Informed System Analysis (RISA) Pathway Page 2 Materials Research Pathway Main Goal: understand and predict long-term behavior of materials in nuclear power plants Latest Report:
Methodological Guidelines for Industry Focusing on Characterization Procedures to Assess the Risk of Irradiation Degradation of Concrete in the Biological Shield-This report summarizes the experimental methods that have been used by the irradiated concrete research community to understand the effects of neutrons on aggregates over the past decade. It is structured so that industry can use it as a guiding methodology to estimate the irradiation damage of their unique concrete formulation over extended operation. Two case scenarios are presented: techniques that can be used if access to unirradiated concrete cores from an NPP is possible and techniques that can be employed if access to irradiated aggregates in test reactors is possible.
Main Goal: develop safety analysis methods and tools to optimize the safety, reliability, and economics of nuclear power plants Latest Report:
Technical Language Processing of Nuclear Power Plants Equipment Reliability Data-Nuclear power plants produce a large amount of equipment reliability data during their regular maintenance operations. Using this data, this newly-developed methodology first cleans up this information and then uses customized technical natural language processing, a type of machine learning, to identify the physical asset, like a pump or motor, a specific phenomenon happening in that asset, like a cracked valve, and what the likely effects will be.
Locations for dimension measurements of irradiated aggregates Example analysis of sentences containing temporal entities (highlighted in purple )
Page 3 LWRS June Calendar Monthly Calls (link on the dates)
FPOG Call-June 3, 2024-Fire protection issues for co-location of a hydrogen facility near a NPP - 10:00-11:00 AM June 24, 2024-Radiation monitoring considerations for co-location of a high temperature hydrogen facility near a nuclear plant. 10:00-11:00 AM Past Issues Prepared by: Ramón L. Gascot (RES/DE/RGPMB)
Main Goal: enable diversification and increase revenue of light water reactors to produce non-electrical products Physical Security Pathway Main Goal: develop technologies and technical bases to optimize physical security Latest Report:
No report for this issue Flexible Plant Operation & Generation (FPOG) Pathway Latest Report:
Design Basis for Control System Implementation in a PWR to Enable 30-100% Thermal Power Extraction-This report provides the additional background and design basis of the reactor coolant system (RCS) average reference temperature for that design effort. The control system considerations to be implemented in a digital implementation in the plant are identified, as well as the devices/components to be controlled and the impacts to existing control systems that need to be considered by end users. This review applies specifically to digital control systems and more specifically, Westinghouse 4-Loop PWRs. The assessment approach is generally applicable to other Nuclear Steam Supply System (NSSS) digital designs. All PWR plants will require a detailed plant specific assessment to determine unit specific modification requirements.