Liquid Metal Fast Reactor Core Thermal-Hydraulics Benchmark (LMFR T/H)
Ongoing
Texas A&M University experimental facility, consisting of a primary loop, which provides the flow for the experiments, and a secondary loop, performing volume control, temperature control, and filtration. Graphics on the right show the three-dimensional representation of the test bundle (one-pitch length) and one acrylic pin as fabricated. Image: Texas A&M University.

Overview

The Liquid Metal Fast Reactor (LFMR) is one of the next generation reactor designs, and many numerical and experimental studies have been performed on LMFR core geometry. To establish best practise guidance for LMFR thermal hydraulics simulations and to compare different numerical appraoches on an international level, a benchmark was prepared jointly by North Carolina State University (NCSU) and Texas A&M University (TAMU), USA, in cooperation with United States Nuclear Regulatory Commission (US NRC) and OECD-NEA. The work is supported by the US NRC (Grant 31310021M0009) and endorsed by the OECD-NEA. The benchmark is part of the Expert Group on Reactor Core Thermal-Hydraulics and Mechanics (EGTHM) activities. 

The LMFR T/H benchmark consists of two Phases:

  • Phase I: Steady-state numerical predictions of Texas A&M University (TAMU) separate effect test and comparison to experimental results; 
  • Phase II: Numerical predictions of the Thermal Hydraulic Out of Reactor Safety (THORS) integral effect tests and comparison to experimental results.

Each phase will include several exercises and will be planned to accommodate as many numerical prediction methods as possible.

Phase I: Steady-state numerical predictions of Texas A&M University (TAMU) separate effect test 

The objectives of Phase I are to provide a detailed geometry of the bundle test section and boundary conditions and a high-resolution experimental database of isothermal turbulent flow and pressure drop acquired from a 61-pin wire-wrapped hexagonal fuel bundle (all from TAMU); assess the performance of numerical schemes and turbulent models currently implemented in the state-of-the-art Computational Fluid Dynamics (CFD) codes; and establish best practices for uncertainty quantification (UQ) of model geometry, initial and boundary conditions, and other associated uncertainties for CFD calculations.

Phase II: Numerical predictions of the Thermal Hydraulic Out of Reactor Safety (THORS) integral effect tests 

The objectives of Phase II are to provide a sodium turbulent flow and heat transfer database for CFD and subchannel model validation; emphasize the importance of uncertainty analysis for TH simulations; establish best practices for quantification of geometry modelling, input data, fluid properties, and other uncertainties associated with the complex flows in LMFR bundles; develop guidance for CFD model/code validation for LMFR fuel bundles that can be used to improve the existing standards; update the current TH models for pressure drop and inter-channel mixing; and develop the hybrid experiment/simulation database necessary to establish and calibrate the low order models with high resolution (both experimental/numerical) data.

Benchmark Organisation

Benchmark coordinator: Maria N. Avramova (USA) and Yassin A. Hassan (USA)

Participants: All NEA member countries  LMFR T/H Participants' working area

Benchmark participation

Access to the benchmark is open to all OECD/NEA member countries and it requires only acceptance of the benchmark conditions.

Please sign the conditions form and send it to the WPRS Secretariat.

Schedule

Contact

WPRS Secretariat