NE Voucher Awards in Progress
The objective is to integrate the core and shielding analysis tools in order to design a safe and economically viable microreactor.
This project seeks to address 1) pressure drop behavior of a typical sodium fast reactor fuel assembly with an orifice device and 2) orifice device onset of cavitation.
The project will evaluate the criticality safety limits of the conceptual equipment designs for NuCycle™.
Criticality Safety Evaluation of NuCycle™, Curio Solutions Read More »
Elementl is evaluating dozens of locations in the U.S. for siting suitability of advanced reactor technologies.
Elementl Power Siting Evaluation, Elementl Power LLC Read More »
TVA has begun planning an Advanced Nuclear Program and is beginning to study future deployment of advanced nuclear reactors (ANRs). This project will screen the TVA service area to help determine suitable sites for future ANR deployment.
TVA Siting Study, Tennessee Valley Authority Read More »
Previous studies for UF6 limits in shipping containers were limited to enrichment up to 5%. The objectives of this new study will take that enrichment to 10%. The project will review the available literature and update these studies with current techniques, evaluate the impact of higher enrichments in safety criticality cases in transport conditions, and publish a report that will serve as the basis to the safety criticality analysis that will be provided for review and approval to the radioactive material transport regulators, for the DN-30 package with 30B cylinders containing enrichment higher than 5%.
LEU+ UF6 Physical Chemistry Study, Orano Federal Services Read More »
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.
This project will include the analysis of fuel performance under Micro Modular Reactor (MMR) operating conditions and assess if using recycled uranium in Fully Ceramic Microencapsulated (FCM) fuel is viable.
This project seeks to perform baseline studies on surface-treated A709 for corrosion resistance and mechanical properties to understand long-term corrosion protection when subject to periods of sustained and cyclic loading at high temperatures and its potential use in the IMSR®.
By leveraging Oak Ridge National Laboratory’s lab capabilities, Ultra Safe Nuclear Corporation will further the efficient deployment and operation of manufacturing modules at their facilities.
