ARC-100 Reactor Probabilistic Safety Analysis Volume 2 – Detailed Modeling and Results
This is an Appendix that will be appended to the main Report body (the main Report is treated separately). This Appendix contains proprietary information and is not intended for public release.
Examples of Risk and Reliability Models using Simulation
Slides for an external presentation at a reliability workshop.
Scenario Exploration and Timeline Analysis for Advanced Reactors
Slides created to discuss the report “Approach and Model Used to Represent a Timeline Analysis for Security Design Enhancements” (August 2022 INL/ RPT-22-68664) for an upcoming DOE security workshop.
Human Reliability Analysis Studies from Simulator Experiments using Bayesian Inference
Probabilistic Safety Assessment (PSA) of complex facilities is performed to arrive at the risk posed by them. PSA also accounts for the contribution of the human errors towards the overall risk through Human Reliability Analysis (HRA) in terms of Human Error Probability (HEP). Human operators are part of the system and do not work in […]
Simulation Environments for Physical Phenomena of Extreme Events
Slides for an external workshop on simulation approaches to risk analysis.
Generic Pressurized Water Reactor Model for SAPHIRE
Generic Pressurized Water Reactor Model for SAPHIRE This report contains a data dump from a SAPHIRE Generic Pressurized Water Reactor (PWR) model. The intent is to have this information reviewed for export control and classification so that the generic model can be used external to INL. The facility model is not applicable to any existing […]
ARC-100 Transient Overpower Scenario Modeling
This report captures the analysis performed for the transient overpower scenario modeling for the ARC-100 reactor.
Approach and Model Used to Represent a Timeline Analysis for Security Design Enhancements
Next-generation reactors will be able to use risk to inform and performance base the licensing of many aspects of the reactor, facility, and site design, including attributes of physical security. There are several factors related to security, including site topography, reactor design, and physical protection system components, to consider when designing the physical protection system […]
Feasibility Study of Developing Alternative Common-Cause Failure Model for Event Assessment
This report is a revision of the original report, INL/LTD-14-33376. The original report, which was a limited distribution to the Nuclear Regulatory Commission (NRC) only and not available to the public, was revised as this report for public distribution. The report presents the feasibility study of alternative common-cause failure (CCF) models that could be used […]