Spotlight
Natrium
Project Overview
The U.S. Nuclear Regulatory Commission (NRC) is currently engaged in pre-application activities interactions for the Natrium reactor. The Natrium design combines features from the previous GEH PRISM and TerraPower Traveling Wave designs. The proposed Natrium reactor is a 345 MWe pool type sodium fast reactor using HALEU metal fuel.
For more information, please see the Natrium pre-application documents (NRC Docket 99902100). Additional TerraPower documents can be found at NRC Docket 99902087.
To subscribe to the TerraPower Natrium email service, select TerraPower Natrium from the Advanced Reactors list after entering your email into the GovDelivery system.
For information about TerraPower’s Molten Chloride Fast Reactor (MCFR), please see the MCFR webpage.
For information related to the NRC staff’s review of Kemmerer Power Station Unit 1 application please see TerraPower, LLC -- Kemmerer Power Station Unit 1 Application
Pre-Application Activities
Product | Type | Reference | Status |
|---|---|---|---|
Regulatory interpretation of the applicability of 10 CFR 50.10 to the construction of the Sodium Test and Fill Facility | White Paper | Feedback Provided | |
Quality Assurance Topical Report (QATR) | Topical Report | Feedback Provided | |
Advanced SFR Fuel Assembly Qualification Plan | White Paper | Feedback Provided | |
Advanced Fuel Qualification Methodology Report-Regulatory Guidance Development Report | White Paper | Feedback Provided | |
TerraPower-Type 1 Fuel Pin Qualification Plan | White Paper | Feedback Provided | |
TerraPower, LLC - Natrium Decoupling Strategy | White Paper | Cancelled | |
TerraPower, LLC, Submittal of Testing Programs | White Paper | Feedback Provided | |
TerraPower, LLC Topical Report, Regulatory Management of Natrium Nuclear Island and Energy Island Design Interfaces | Topical Report | Feedback Provided | |
Revised TerraPower, LLC Quality Assurance Topical Report, Revision 14 | Topical Report | Feedback Provided | |
TerraPower, LLC, Regulatory Gap Analysis Report | White Paper | Feedback Provided | |
Principal Design Criteria for the Natrium Advanced Reactor | Topical Report | Feedback Provided | |
Fuel and Control Assembly Qualification Plan | Topical Report | Feedback Provided | |
Nascent Thermal Hydraulic Model White Paper | White Paper | Feedback Provided | |
Plume Exposure Pathway Emergency Planning Zone Methodology, Revision 3 | Topical Report | Feedback Provided | |
An Analysis of the Potential Volcanic Hazards at the Proposed Natrium Site Near Kemmerer, Wyoming | Topical Report | Feedback Provided | |
Human Factors Engineering Program Plan and Methodologies | Topical Report | Feedback Provided | |
Human Factors Engineering (HFE) Concept of Operations | White Paper | Feedback Provided | |
Preliminary Consensus Codes and Standards | White Paper | Feedback Provided | |
Radiological Source Term Methodology Report, Revision 1 | Topical Report | Feedback Provided ML25211A271 | |
Design Basis Accident Methodology for In-Vessel Events without Radiological Release | Topical Report | Feedback Provided | |
Radiological Release Consequences Methodology | Topical Report | Feedback Provided | |
Reactor Stability Methodology | Topical Report | Feedback Provided | |
Partial Flow Blockage Methodology | Topical Report | Feedback Provided | |
Design Basis Accident Methodology for Events With Release | Topical Report | Feedback Provided | |
Reactor Seismic Isolation System Qualification | Topical Report | Under Review | |
Instrumentation and Control Architecture and Design Basis | Topical Report | Feedback Provided |
Page Last Reviewed/Updated Wednesday, September 24, 2025
Page Last Reviewed/Updated Wednesday, September 24, 2025