Summary Report Of The FY25 Reactor Physics Verification And Validation Exercises In The Advanced Reactor Technologies – Gas-cooled Reactor Program
Valdiation and verification of numerical tools is critical for ensuring reasonable predictions for design scoping, licensing, and safety analsyis. In this report, two reactor physics verification and validation exercises are presented. The first of these exercises focuses on burnup analysis with data from the Advanced Gas Reactor (AGR) program. Simulations are performed with Monte Carlo […]
A Generalized Nuclear Code of Accounts for Cost Estimation Standardization
This is a joint INL-EPRI study. Link to corresponding page at the Electric Power Research Institute (EPRI): https://www.epri.com/research/products/000000003002028937 Note that an Excel spreadsheet is included in PDF Attachment Abstract: Recent Advanced Reactor (AR) designs typically offer features and attributes that depart from traditional water-cooled reactors in terms of fuel forms, coolants, structural materials, size, safety […]
Meta-Analysis of Advanced Nuclear Reactor Cost Estimations
Supporting Data can be downloaded at: https://gain.inl.gov/content/uploads/4/2024/06/INL-RPT-24-77048-R1.xlsx Nuclear energy is a critical cornerstone of the current United States clean energy supply and may play a larger role in the future in support of a transition to a net-zero economy. The current fleet of nuclear reactors predominantly consists of large light-water reactors (LWRs), while many of […]
Sodium-Cooled Fast Reactor Reference Plant Model
This report details the progress of INL on the creation of a reference plant multiphysics model for the ABTR. The model was developed within Task 13 of the NRC project “Development and Modeling Support for Advanced Non-Light Water Reactors” and is an extension of the reference plant developed in Task 4b. Several improvements were made […]
Progress toward the development of a high-fidelity neutronic model of MARVEL using Griffin
The Microreactor Applications Research Validation and Evaluation (MARVEL) is a 100 kWth microreactor envisioned to start operations at Idaho National Laboratory (INL) in early 2025. This paper is focused on the development of a high-fidelity neutronic model of the MARVEL reactor using Griffin. In particular, the step-by-step verification procedure against Serpent reference calculations is here […]
Development and Application of two-step Uncertainty Propagation and Sensitivity Analysis Methodology for Fast Reactor Safety Analysis
Uncertainty quantification (UQ) in nuclear reactors for transients is directly linked with safety assessment through the cross-sections uncertainties, provided as a covariance matrix, which are propagated through the reactor system to output of interest pertaining to reactor safety, such as peak temperatures in fuel/clad/coolant. Using a two-step approach, uncertainties are first quantified and propagated from […]