Completed NE Voucher Awards
The benchmarks, analytical solutions, and failure criteria developed during this project will be used directly by USNC-Tech to evaluate the current graphite core design of the MMR™ reactor, resulting in an optimized core and a down-selection of the graphite used for the core.
Graphite Finite Element Model Verification, Ultra Safe Nuclear Corporation Read More »
The objective of this project was to analyze reactor core and system behavior in response to anticipated transients and accident scenarios and to use the Virtual Environment for Reactor Applications (VERA) code suite, which employs multi-physics simulation to model feedback behavior in the reactor core.
To broaden the understanding of fuel-clad chemical interactions (FCCI), Oklo partnered with Idaho National Laboratory (INL) to conduct an out-of-pile experimental investigation into FCCI behavior that addresses each of these variables in order to expand the operating envelopes to better align with the Aurora reactor as well as other advanced concepts.
Addressing Gaps in Legacy Data on Fuel Steel Interactions, Oklo, Inc. Read More »
The scope of this project included the design of an experiment for irradiating Lightbridge metallic fuel material samples in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL).
The objective of this project was to use the thermal hydraulics laboratory and vacuum test chambers at Oak Ridge National Laboratory (ORNL) for response characterization of resistance temperature detectors and thermal aging of instrumentation and control (I&C) cables in vacuum to generate more useful data for I&C cable derating purposes.
Westinghouse Electric Company and Oak Ridge National Laboratory designed and performed an experiment to develop a non-destructive assay measurement method that addressed the challenges of the volumetric deposits within the large ventilation system housings.
Kairos collaborated with Argonne National Laboratory (ANL) to develop design rules and associated materials data for the design of cladded components made of Type 316 stainless steel and cladded by non-code qualified corrosion resistant materials.
Framatome used failure modes and effects analysis (FMEA) to determine and define potential failure mechanisms for the U-50Zr alloy design.
Advanced Metallic U-Zr Fuel for LWR Applications – FMEA and PIRT Development, Framatome Read More »
The objective of this project was to provide FEI with design recommendations for the implementation of nuclear material accountancy and enable FEI to meet its sustainability and operational goals for the LFTR.
Liquid Fluoride Thorium Reactor (LFTR) Preliminary Safeguards Assessment, Flibe Energy Read More »
The goal of this project was to develop a method for analyzing the oxygen content using a commercial inert gas fusion analyzer. This included the development of a calibration curve for the method, quantification of its performance, and testing on FLiBe samples from several sources, including ORNL-produced FLiBe as well as Kairos Power Flibe.
Chemical Method Development for Quantifying Oxygen in Beryllium Salts, Kairos Power Read More »
