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Willit, James

Publications and source records attributed to Willit, James.

Synthesis of Molten Chloride Salt Fast Reactor Fuel Salt from Spent Nuclear Fuel (CRADA 2017-17170 Final Report)

Elysium Industries USA, Inc. aims to produce safe, cost effective, carbon conscious energy through the development of an advanced liquid-fueled reactor technology. The Elysium liquid-fueled reactor concept comprises a molten chloride salt fueled fast spectrum nuclear reactor, which can accept fissle material recovered from used nuclear fuel and excess fissile material from defense applications. A key technology development need for the system is demonstrating the feasibility of a low cost, efficent method to produce the chloride fuel salt from used nuclear fuel. This approach not only provides a pathway for the disposition of used nuclear but more efficient use of uranium resources for energy production.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Development of a Pyroprocessing Flowsheet Model for Safeguards Analysis

Pyroprocessing flowsheets have been designed that have efficient actinide recovery, meet nonproliferation objectives, minimize waste, and are commercially viable. The analysis of safeguards of pyrochemical recycle systems for the treatment of used fast reactor metal fuel can be greatly enhanced with the employment of robust dynamic models. Electrochemical process modeling also contributes to broader objectives of the MPACT program by supporting MC&A, options screening, and safeguards analysis and can inform development of sensor systems for a used fuel recycle facility. Modeling can also provide a method for defining metrics and requirements on advanced analysis techniques.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗