Organization: Sandia National Laboratory

Overcoming the Material-Growth Barrier for Fabrication

Srijan will work with Sandia National Laboratories (SNL) to grow thick-film hBN using carbon-free precursors such as boron tribromide and borazine, enabling the material quality needed for neutron detector applications. SNL possesses specialized chemical vapor deposition (CVD) reactor facilities and expertise in carbon-free hBN epitaxial growth that are unavailable commercially and the laboratory’s advanced characterization capabilities, including XRD, SIMS, and Raman spectroscopy, are also essential for validating impurity levels and semiconductor performance.

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Safeguards and Security by Design Workshop

Los Alamos National Laboratory and Sandia National Laboratories in New Mexico September 25-29, 2023 The National Nuclear Security Administration (NNSA) is organizing a five-day Safeguards and Security by Design workshop for U.S. advanced and small modular reactor (ASMR) vendors/developers that seek to deploy their technologies in the U.S. and abroad. REGISTRATION DETAILS:  Recommended attendees include safeguards and security directors and system designers, license application managers, and plant designers. The workshop is for U.S. citizens only. Registration closes on July 31,

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Characterization of the Radiation Stability of Molten Nitrate/Nitrite Salts for use as Heat Transfer Fluids in Nuclear Reactor Power Plants, Yellowstone Energy

The objective of this project is to complete the necessary irradiation testing required and accelerate the retirement of risk related to qualification of nuclear environment nitrate salts. It is expected that the results of this project will significantly advance the MNSR design by qualifying the radiation stability of nitrate salt coolants in a nuclear environment.

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Risk-Informed Mechanistic Source Term Calculations for a Compact Fast Reactor, Oklo Inc.

The objective of this project was to focus on the coupling of three high fidelity analysis codes for detailed core analysis, an analysis of the Oklo reactor design to assesses the potential for radionuclide release to the environment during accident scenarios, and an assessment and provision of relevant metal fuel data through inspection of post-irradiation examination data from past metal fuel testing. This project had two additional objectives, the experimental characterization of liquid metal heat pipe performance, failure behavior, and phenomena and the testing of generic heat pipes beyond their design limits, providing original data and insights.

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