6230 Light Water Reactors Systems Course Part 1
Abstract not provided.
Publications
Discrete Dynamic Event Tree Analysis of Small Modular Reactor Severe Accident Management
Abstract not provided.
LEVERAGING EXISTING TOOLS FOR SIMULATING OPERATOR PERFORMANCE IN DISCRETE DYNAMIC EVENT TREES
Abstract not provided.
Proof of Principle Framework for risk informed Severe Accident Management Guidelines
Abstract not provided.
Discrete Dynamic Event Tree Analysis of Small Modular Reactor Severe Accident Management
Abstract not provided.
Evaluation of the applicability of existing nuclear power plant regulatory requirements in the U.S. to advanced small modular reactors
The current wave of small modular reactor (SMR) designs all have the goal of reducing the cost of management and operations. By optimizing the system, the goal is to make these power plants safer, cheaper to operate and maintain, and more secure. In particular, the reduction in plant staffing can result in significant cost savings. The introduction of advanced reactor designs and increased use of advanced automation technologies in existing nuclear power plants will likely change the roles, responsibilities, composition, and size of the crews required to control plant operations. Similarly, certain security staffing requirements for traditional operational nuclear power plants may not be appropriate or necessary for SMRs due to the simpler, safer and more automated design characteristics of SMRs. As a first step in a process to identify where regulatory requirements may be met with reduced staffing and therefore lower cost, this report identifies the regulatory requirements and associated guidance utilized in the licensing of existing reactors. The potential applicability of these regulations to advanced SMR designs is identified taking into account the unique features of these types of reactors.
LEVERAGING EXISTING TOOLS FOR SIMULATING OPERATOR PERFORMANCE IN DISCRETE DYNAMIC EVENT TREES
Abstract not provided.
NEST Fact Sheets- Part II
Abstract not provided.
Treatment of uncertainties associated with PRAs in risk-informed decision making (NUREG-1855)
Proceedings of Risk Management - For Tomorrow's Challenges
Abstract not provided.
Introduction to Nuclear Safety
Abstract not provided.
Probabilistic Risk Assessment (PRA) Presentation to Study Tour for Chinese PUNT Delegation
Abstract not provided.
Cassini Spacecraft Uncertainty Analysis Data and Methodology Review and Update/Volume 1: Updated Parameter Uncertainty Models for the Consequence Analysis
Uncertainty distributions for specific parameters of the Cassini General Purpose Heat Source Radioisotope Thermoelectric Generator (GPHS-RTG) Final Safety Analysis Report consequence risk analysis were revised and updated. The revisions and updates were done for all consequence parameters for which relevant information exists from the joint project on Probabilistic Accident Consequence Uncertainty Analysis by the United States Nuclear Regulatory Commission and the Commission of European Communities.
A multi-attribute utility decision analysis for treatment alternatives for the DOE/SR aluminum-based spent nuclear fuel
Risk Analysis
A multi-attribute utility analysis is applied to a decision process to select a treatment method for the management of aluminum-based spent nuclear fuel (Al-SNF) owned by the US Department of Energy (DOE). DOE will receive, treat, and temporarily store Al-SNF, most of which is composed of highly enriched uranium, at its Savannah River Site in South Carolina. DOE intends ultimately to send the treated Al-SNF to a geologic repository for permanent disposal. DOE initially considered ten treatment alternatives for the management of Al-SNF, and has narrowed the choice to two of these: the direct disposal and melt and dilute alternatives. The decision analysis presented in this document focuses on a formal decision process used to evaluate these two remaining alternatives.
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