New Virtual Test Bed Capabilities: Virtual DOME Model and New Updates to Repository

Technical Report · Sat Aug 31 04:00:00 EDT 2024

DOI:https://doi.org/10.2172/2478528· OSTI ID:2478528

Charlot, Lise ^[1]; Mohammad Jaradat, Mustafa Kamel ^[1]; Elkamash, Mohamed ^[2]; Giudicelli, Guillaume Louis ^[1]; Abou Jaoudé, Abdalla ^[1]; Shemon, Emily ^[3]; Kumar, Shikhar ^[3]; Dorville, Joffrey ^[3]

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1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
2. Univ. of Illinois at Urbana-Champaign, IL (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)
3. Argonne National Laboratory (ANL), Argonne, IL (United States)

The Department of Energy (DOE) Office of Nuclear Energy National Reactor Innovation Center accelerates the deployment of novel reactor concepts by establishing both physical and virtual spaces for building and testing various components, systems, and complete pilot plants. The Virtual Test Bed represents the virtual arm of the National Reactor Innovation Center and is a joint effort with the DOE Nuclear Energy Advanced Modeling and Simulation Program. The Virtual Test Bed mission is to accelerate the deployment of advanced reactors by facilitating the adoption of cutting-edge DOE advanced modeling and simulation tools to design, evaluate, and license reactors. This is primarily achieved by storing example challenge problems in an externally available repository and by developing models to fill the M&S gaps needed for potential demonstrators. Activities conducted this fiscal year focused on developing of a Demonstration of Microreactor Experiments shield model to help accelerate the confirmatory analysis required for the reactor demonstration. This model and workflow will allow developers to leverage advanced modeling and simulation tools to ensure their reactor demonstration concept will meet dose requirements and that the surrounding shield will stay within concrete temperature limits during steady-state and transient operation conditions. An initial model has been developed to evaluate the temperature distribution in the concrete shield during steady-state operation, including neutron and gamma heating effects. Various modeling strategies have been examined to understand their applicability and limitations with different reactor designs to make the workflow as reactor-agnostic as possible and computationally effective to maximize its usability. In addition to describing the Demonstration of Microreactor Experiments shield model and associated results, this report summarizes other accomplishments regarding repository maintenance and improvement and new external models hosted on the repository.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 2478528
• Report Number(s): INL/RPT--24-80131-Rev000
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
Heat Transfer
Neutron and Gamma Heating
Shield