How to predict and prevent radioactive release in FHRs: Experiments, modeling and simulation of tritium adsorption systems Stephen Lam, Ronald Ballinger, Charles Forsberg Massachusetts Institute of Technology Codes simulate integrated effects and mitigation strategies System response across design and operating conditions in column SYSTEM DYNAMICS AND OPTIMIZATION ACKNOWLEDGEMENTS INFORMED SIMULATION 1.The Fluoride High-Temperature Salt-Cooled Reactor (FHR) uses Lithium-based molten salts 2.Neutronic reaction of Lithium generates radioactive tritium ( 1 3 HF and 1 3 H 2 ) 3.Tritium diffusion to environment causes radioactive release of 2400 Ci/d (for 236 MWth reactor) 4.Experiments coupled to simulation used to develop effective tritium adsorbents Transport properties at reactor conditions predict in-situ behavior ABSTRACT EXPERIMENTAL DATA AND INSIGHTS Nuclear Technology, Vol. 197 - 2, p.119-139, 2017 Journal of Nuclear Materials, Vol. 511, p.328-340, 2018 Nanoporous Carbon Tritium Retention Thermodynamic Isotherms Operational Behavior Reversibility of Adsorption Thermodynamic Modeling Mechanisms and Predictions System Inventory Radioactive upkeep distribution Understanding tritium interactions on materials Experiments, modeling and simulation used to predict tritium behavior and enable iterative material design Adsorbents can reduce radioactive release by more than 95% and inventory by more than 70% KEY CONCLUSIONS Coupled Multi-physics Reaction and Transport Dynamic Simulation Time dependence Shanghai Institute of Applied Physics of the Chinese Academy of Sciences Material Characterization Adsorption and desorption Thermo-kinetic sorption behavior Compositional analysis Reaction species and rate determination EXPERIMENTAL AND MATERIAL DESIGN Morphological Analysis Microstructure Determination Release Rate Peak atmospheric rate Max Release Rate (Ci/day) Material Performance Transport regime and limits REFERENCES

How to predict and prevent radioactive release in FHRs

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How to predict and prevent radioactive release in FHRs:

Experiments, modeling and simulation of tritium adsorption systemsStephen Lam, Ronald Ballinger, Charles Forsberg

Massachusetts Institute of Technology

Codes simulate integrated effects and mitigation strategies

System response across design and operating conditions in column

SYSTEM DYNAMICS AND OPTIMIZATION

ACKNOWLEDGEMENTS

INFORMED SIMULATION

1.The Fluoride High-Temperature Salt-Cooled Reactor (FHR) uses Lithium-based molten salts

2.Neutronic reaction of Lithium generates radioactive tritium (13HF and 1

3H2)

3.Tritium diffusion to environment causes radioactive release of 2400 Ci/d (for 236 MWth reactor)

4.Experiments coupled to simulation used to develop effective tritium adsorbents

Transport properties at reactor conditions predict in-situ behavior

ABSTRACT

EXPERIMENTAL DATA AND INSIGHTS

Nuclear Technology, Vol. 197 - 2, p.119-139, 2017

Journal of Nuclear Materials, Vol. 511, p.328-340, 2018

Nanoporous Carbon

Tritium RetentionThermodynamic Isotherms

Operational BehaviorReversibility of Adsorption

Thermodynamic ModelingMechanisms and Predictions

System InventoryRadioactive upkeep distribution

Understanding tritium interactions on materials

Experiments, modeling and simulation used to predict tritium behavior and enable iterative material design

Adsorbents can reduce radioactive release by more than 95% and inventory by more than 70%

KEY CONCLUSIONS

Coupled Multi-physicsReaction and Transport

Dynamic SimulationTime dependence

Shanghai Institute of Applied Physics of the Chinese Academy of Sciences

Material Characterization

Adsorption and desorptionThermo-kinetic sorption behavior

Compositional analysisReaction species and rate determination

EXPERIMENTAL AND MATERIAL DESIGN

Morphological Analysis

Microstructure Determination

Release RatePeak atmospheric rate

x R

ele

ase

te (

Ci/d

ay)

Material PerformanceTransport regime and limits

REFERENCES

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