Pacific Northwest National Laboratory Archives

High-Temperature Pipe Wall-Thickness Detection System

Nuclear AI will partner with Pacific Northwest National Laboratory (PNNL) to utilize the capabilities for the Nondestructive Evaluation Unit of the Engineering Materials group. PNNL will use high-temperature furnace infrastructure, ultrasonic PZT sensor components, and high precision prototyping equipment to demonstrate the efficacy of a high temperature pipe wall thickness detector. The ability to perform inspections and vet structural integrity at these temperatures would support advanced reactor inspection programs for piping and vessel components.

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Development of Novel Deconversion Technology

Oklo will partner with Pacific Northwest National Laboratory (PNNL), which has demonstrated gram-scale reduction of UF6 to UF4 through an intermediary compound that significantly reduces the traditional method’s hazards. PNNL has also shown the viability of co-reducing fluorides to metal. The possibility of eliminating the intermediate UF4 production step will have the potential of increased throughput and process safety that will help accelerate deployment of a commercial fabrication facility.

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Radiation Test of Smart Electric Cable for Nuclear Power Plants

AiMiLi will partner with Pacific Northwest National Laboratory (PNNL) to access the Accelerated and Real-time Experimental Nodal Assessment (ARENA) Cable Test Bed and High Exposure Facility (HEF) gamma irradiation capabilities. These facilities can simulate adverse power plant environments in a testing environment.

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Development of Analytical Techniques for Trace Impurities in 2LiF-BeF2, Kairos Power

Kairos will partner with Pacific Northwest National Laboratory (PNNL) to extend measurements of dissolved oxygen and corrosion products in FLiBe to the full range of relevant/significant impurities, as well as incorporating the measurement methods into their quality assurance program/practices. Refinement of analytical methods for species in salt that impact system operation will enable Kairos to continue along the aggressive timeline for near term nuclear demonstration and commercial deployment.

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Analysis of NuCycle® Flowsheet for Waste Stream Characterization, Curio Solutions

Curio will partner with Pacific Northwest National Laboratory (PNNL) to conduct an analysis of the NuCycle® flowsheet that will allow the generation of quantities and classification of anticipated waste streams and recommendations on waste forms most suitable to sequestering the generated waste streams. Results of the project would be used to determine the approach to managing waste from a pilot demonstration of NuCycle® to be performed in 2027.

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ICP-MS for Analysis of Lithium Isotopic Ratios in Materials Highly Enriched in 7Li, Kairos Power

The goal of this project would be to evaluate performance capabilities of instruments and develop standardized hardware configurations and operating procedures to analyze lithium isotopic ratios to support production of Flibe coolant that is highly enriched in 7Li.

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PIE-Enabled Study of Aqueous Corrosion & Zr Hydriding in Cr-Coated Cladding, Westinghouse

The objective of this project is to enhance understanding of aqueous corrosion and hydrogen transport for Zr hydride formation in Cr-coated claddings, as a function of the Cr-coating deposition method (cold spray (CS) or physical vapor deposition (PVD)).

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Advanced Functional Membrane Testing for Noble Gas Management in a Molten Salt Reactor, Exodys Energy (Elysium)

The objective of this project is to evaluate a metalorganic framework (MOF) for continuous separation of Xe and Kr from the off-gas in the FCMSR in order to optimize the noble gas management of the FC-MSR and chemical processes for fuel salt production and conditioning and support the safety and licensing bases.

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Lead-Bismuth Small Modular Reactor (SMR) Licensing Development; Methodology for Meeting Containment System Principal Design Criteria for Heavy Metal Fast Reactor systems, Columbia Basin Consulting Group

The objective of this project was to review Columbia Basin Consulting Group (CBCG)’s design concept for a leadbismuth-cooled fast reactor and thereafter to determine how the design might benefit from the functional containment concept, which allows the designer to take credit for a sequence of barriers to contain or confine radionuclides.

Lead-Bismuth Small Modular Reactor (SMR) Licensing Development; Methodology for Meeting Containment System Principal Design Criteria for Heavy Metal Fast Reactor systems, Columbia Basin Consulting Group Read More »