NDLI: Fast Reactor Design Using the Advanced Reactor Modeling Interface

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Cheatham, Jesse Truong, Bao Touran, Nicholas Latta, Ryan Reed, Mark Petroski, Robert
Copyright Year	2013
Abstract	The Advanced Reactor Modeling Interface (ARMI) code system has been developed at TerraPower to enable rapid and robust core design. ARMI is a modular modeling framework that loosely couples nuclear reactor simulations to provide high-fidelity system analysis in a highly automated fashion. Using a unified description of the reactor as input, a wide variety of independent modules run sequentially within ARMI. Some directly calculate results, while others write inputs for external simulation tools, execute them, and then process the results and update the state of the ARMI model. By using a standardized framework, a single design change, such as the modification of the fuel pin diameter, is seamlessly translated to every module involved in the full analysis; bypassing error-prone multi-analyst, multi-code approaches. Incorporating global flux and depletion solvers, subchannel thermal-hydraulics codes, pin-level power and flux reconstruction methods, detailed fuel cycle and history tracking systems, finite element-based fuel performance coupling, reactivity coefficient generation, SASSYS-1/SAS4A transient modeling, control rod worth routines, and multi-objective optimization engines, ARMI allows “one click” steady-state and transient assessments throughout the reactor lifetime by a single user. This capability allows a user to work on the full-system design iterations required for reactor performance optimizations that has traditionally required the close attention of a multi-disciplinary team. Through the ARMI framework, a single user can quickly explore a design concept and then consult the multi-disciplinary team for model validation and design improvements. This system is in full production use for reactor design at TerraPower, and some of its capabilities are demonstrated in this paper by looking at how design perturbations in fast reactor core assemblies affect steady-state performance at equilibrium as well as transient performance. Additionally, the pin-power profile is examined in the high flux gradient portion of the core to show the impact of the perturbations on pin peaking factors.
Sponsorship	Nuclear Engineering Division
File Format	PDF
ISBN	9780791855799
DOI	10.1115/ICONE21-16815
Volume Number	Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors
Conference Proceedings	2013 21st International Conference on Nuclear Engineering
Language	English
Publisher Date	2013-07-29
Publisher Place	Chengdu, China
Access Restriction	Subscribed
Subject Keyword	Equilibrium (physics) Pareto optimization Systems analysis Fuels Modeling Steady state Engines Transients (dynamics) Design Errors Simulation Fast neutron reactors Model validation Teams Nuclear fuel cycle Nuclear reactors Thermal hydraulics
Content Type	Text
Resource Type	Article

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