Design and License Application Development for TRISO-X: A Cross-Cutting, High Assay Low Enriched Uranium Fuel Fabrication Facility

  • Pappano, Pete (PI)
  • Husser, Dewayne D. (CoPI)
  • Krich, Rod R. (CoPI)
  • Mcclure, Mark M. (CoPI)
  • Carmichael, Ben B. (CoPI)
  • Wright, David D. (CoPI)
  • Flanagan, George (CoPI)

Project: Research

Project Details

Description

The proposed Project has four main tasks: 1) conduct studies to assess fuel design and utility/operator requirements for all ARs, 2) using these studies as key inputs, complete the preliminary and final designs of the TRISO-X Facility, 3) complete the license application for this facility, and 4) complete the licensing application process with the NRC and obtain acceptance and docketing of the application submittal. We expand on these four primary tasks below: 1. Feasibility Studies: Perform three feasibility studies, including (a) reactor fuel element requirements analysis; (b) utility/operator fuel requirements analysis, and (c) concept design of the second-most likely fuel form process module (in addition to pebbles). The information in these studies informs the layout of the TRISO-X Facility production modules and the scope of CAT II license application. 2. Fuel Fabrication Facility Preliminary and Final Design Development: Continue our design activities for developing the TRISO-X Facility that supports the fabrication of TRISO-based fuel elements to enable the first core and refueling requirements of U.S. ARs. We completed conceptual design of a pebble specific facility in March 2017; once we receive funding we can complete the Preliminary Design and Final Design of our CAT II facility, which can service all ARs. The facility focuses first on common kernel and TRISO production to support pebble fuel forms; we include space for the modular expansion of production equipment for additional fuel element forms. 3. NRC Fuel Facility License Application Development: Develop our NRC license application, including conducting siting alternatives analysis, developing the Safety Program Description (SPD), Environmental Report (ER), Security Plan (SP), and Emergency Plan (EPlan), as well as proactively engaging and working with the NRC prior to the post-submittal review process. 4. NRC Review and Interaction: Continue formal dialogue with the NRC following submission of the license application to ensure our application is accepted and docketed.
StatusActive
Effective start/end date01/1/18 → …

Funding

  • Office of Nuclear Energy

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