Publication | Open Access
PBMR-400 BENCHMARK SOLUTION OF EXERCISE 1 AND 2 USING THE MOOSE BASED APPLICATIONS: MAMMOTH, PRONGHORN
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Citations
7
References
2021
Year
EngineeringNuclear PhysicsPebble Bed ReactorsReactor DesignReactor PhysicsNew GenerationNuclear Reactor DesignReactor AnalysisKinesiologySystems EngineeringBiostatisticsModeling And SimulationThermodynamicsNuclear Reactor OperationNuclear ReactorsHigh Temperature GasHeat TransferNuclear EngineeringNuclear PowerNuclear EnergyComputational ScienceThermal HydraulicsNuclear Reactor EngineeringAnd 2Nuclear SafetyReactor SafetyReactor Validation
High‑temperature gas‑cooled pebble‑bed reactors are promising Gen‑IV systems but face challenges such as continuous burnup distribution, complex radiative heat transfer, and long transients. The study aims to demonstrate the importance of modeling and simulation for the safety and design of pebble‑bed reactors. The authors used INL’s MAMMOTH multiphysics and Pronghorn thermal‑hydraulics codes within the MOOSE framework to solve Phase 1 exercises 1 and 2 of the OECD NEA PBMR‑400 benchmark. Steady‑state results agree with other participants, confirming that MAMMOTH and Pronghorn can accurately simulate pebble‑bed reactors.
High temperature gas cooled reactors (HTGR) are a candidate for timely Gen-IV reactor technology deployment because of high technology readiness and walk-away safety. Among HTGRs, pebble bed reactors (PBRs) have attractive features such as low excess reactivity and online refueling. Pebble bed reactors pose unique challenges to analysts and reactor designers such as continuous burnup distribution depending on pebble motion and recirculation, radiative heat transfer across a variety of gas-filled gaps, and long design basis transients such as pressurized and depressurized loss of forced circulation. Modeling and simulation is essential for both the PBR’s safety case and design process. In order to verify and validate the new generation codes the Nuclear Energy Agency (NEA) Data bank provide a set of benchmarks data together with solutions calculated by the participants using the state of the art codes of that time. An important milestone to test the new PBR simulation codes is the OECD NEA PBMR-400 benchmark which includes thermal hydraulic and neutron kinetic standalone exercises as well as coupled exercises and transients scenarios. In this work, the reactor multiphysics code MAMMOTH and the thermal hydraulics code Pronghorn, both developed by the Idaho National Laboratory (INL) within the multiphysics object-oriented simulation environment (MOOSE), have been used to solve Phase 1 exercises 1 and 2 of the PBMR-400 benchmark. The steady state results are in agreement with the other participants’ solutions demonstrating the adequacy of MAMMOTH and Pronghorn for simulating PBRs.
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