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Meeting 2025 TMS Annual Meeting & Exhibition
Symposium Special Topics in Nuclear Materials: Lessons Learned; Non-Energy Systems; and Coupled Extremes
Presentation Title Advancing Radioisotope Heat Sources: Enhancing RPS for Extreme Environments
Author(s) Jacob Matthews, Alexander Gilbert, Harsh S. Desai
On-Site Speaker (Planned) Jacob Matthews
Abstract Scope In October 2023, Zeno Power demonstrated a novel, commercial strontium-90 heat source with lower radiation signature compared to heritage systems – called Z1. The Z1 technology demonstration achieved four goals: 1) build nuclear hardware, 2) confirm Zeno Power’s patented approach, 3) confirm Zeno Power’s heat source fabrication techniques from benchtop to nuclear facility, and 4) validate Zeno Power’s computational models with experimental data. Zeno Power is now building the Z2 heat source, a scaled-up, optimized heat source for government contracts supporting space and seabed applications - highlighting its versatility in any environment. Additionally, this technology reduces liability from used nuclear fuel, recycles this fuel for beneficial uses, and revitalizes communities and industries. This paper details the development of the strontium-90 heat source technology from concept to nuclear hardware in under five years, successful demonstration at a national lab, and how heritage strontium-90 sources are being recycled to power next-generation applications.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, High-Temperature Materials,

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advancing Radioisotope Heat Sources: Enhancing RPS for Extreme Environments
Atomistic Simulation of Thermal and Irradiation Creep Mechanisms in BCC-Fe and FCC-Ni using Defect Rate-Based Long-time Dynamics
Best Practices for Irradiation Experiment Design For Nuclear Fuels and Materials Research
Cavity Formation Induced by Swift Heavy Ion Irradiation in AlN/GaN
Comparison of Hardening and Microstructures of Structural Alloys Irradiated with Fast Neutrons and Dual Ions
Developing a High-Performance Cluster Dynamics Code: Challenges and Lessons Learned
Effect of Applied Stress on Radiation-Induced Loop and Raft Formation in a BCC Metal
Effect of Tensile Stress Gradients on the Multi-Length-Scale Microstructure in Thermal and Irradiation Creep of 316L Stainless Steel
Energy Dispersive X-Ray Spectroscopy (EDS) Induced Defects and Implantation Induced Impurities in Uranium Nitride (UN) and SIMFUEL Pellets
Fabrication of Titanium-Containing Tri-Carbide Ultra-High Temperature Ceramics
GIRAFFE – In Situ Material TestsUnder Fusion-Relevant Conditions
In-situ Electron Microscopy Characterization of Deformation Mechanisms of Inconel 718 Irradiated with Simultaneous High Energy Protons and Spallation Neutrons
Influence of Radiation Swelling on Residual Stresses and Measurement of Micromechanical Properties
Materials Research for High-Power Accelerator Beam-Intercepting Devices
Modeling Galvanic Drawdown Separations Technique
Phase Field Modeling of Irradiation-Induced Amorphous-to-Crystalline (A-C) Transformations in Structural Ceramics
Post Irradiation Examination and Administrative Lifetime Limits of Highly Irradiated Components at The Spallation Neutron Source
Small Scale Tests, Big Lessons Learned
The Recovery of Irradiation Damage for Zircaloy-2 and Zircaloy-4 following Irradiation at Higher Temperatures of 377-410°C

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