Published 2017 | Version v1
Miscellaneous Open

U.S. DOE NEAMS Program and SHARP Multi-Physics Toolkit for High-Fidelity SFR Core Design and Analysis

  • 1. Argonne National Laboratory (ANL), Argonne, IL (United States)

Description

Under the U.S. DOE's Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, 3-D, high-fidelity multi-physics simulation capabilities are being developed to address the needs of designers and analysts in studying advanced reactor systems with a particular focus on sodium-cooled fast reactors (SFRs). Simulation-based High-fidelity Advanced Reactor Prototyping (SHARP) is a tool-kit developed under the Reactors Product Line of NEAMS, and it consists of pin-by-pin neutronics, thermal-hydraulics, and structural mechanics analysis modules, as well as the capabilities to integrate these modules for multi-physics calculations. Physics modules currently include the PROTEUS neutronics code with associated cross section generation and evaluation components, the Nek5000 computational fluid dynamics (CFD) code for thermal-hydraulics, and the DIABLO implicit finite element analysis code for structural mechanics. Each module can be utilized as a standalone code component or as part of an integrated analysis. The Reactor Product Line also supports the development of the advanced reactor Systems Analysis Module (SAM), the multigroup cross section generation module MC2-3, and the perturbation and sensitivity analysis module PERSENT. The development philosophy for the modules is to incorporate as much fundamental physics as possible in order to extend functionality to general reactor types, rather than developing tools for a limited set of specific reactor analysis applications. (author)

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Part of:
International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Programme and Papers

Additional details

Publishing Information

Imprint Title
International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Programme and Papers
Imprint Pagination
vp.
Journal Page Range
10 p.
Report number
IAEA-CN--245

Conference

Title
International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
Acronym
FR17
Dates
26-29 Jun 2017
Place
Yekaterinburg (Russian Federation)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
49085746
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; FINITE ELEMENT METHOD; REACTOR DESIGN; SENSITIVITY ANALYSIS; SODIUM COOLED REACTORS; SYSTEMS ANALYSIS; THERMAL HYDRAULICS
Descriptors DEC
CALCULATION METHODS; DESIGN; FLUID MECHANICS; HYDRAULICS; LIQUID METAL COOLED REACTORS; MATHEMATICAL SOLUTIONS; MECHANICS; NUMERICAL SOLUTION; REACTOR LIFE CYCLE; REACTORS; SIMULATION

Optional Information

Notes
27 refs., 2 figs.
Secondary number(s)
IAEA-CN--245-054