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The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Natrium

Artist rendering of Natrium reactor design showing the following components, Reactor Aux. Building, IAC - Intermediate Air Cooling, RVACS - Reactor Vessel Auxiliary Ducts, Reactor Building, Refueling access Area, Fuel Handling Building, Used Fuel, Water Pool, Head Access Area, Reactor and Core, Hot Pip, Cold Pip, RVACS Basement Area. Also displaying Hitachi and Terra Power Logos


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 ML22154A564 Feedback Provided
ML22174A425
Quality Assurance Topical Report (QATR) Topical Report ML21005A015 Feedback Provided
ML22018A301
ML22018A300
ML21263A236
Advanced SFR Fuel Assembly Qualification Plan White Paper ML20316A038 Feedback Provided
ML21099A081         
Advanced Fuel Qualification Methodology Report-Regulatory Guidance Development Report White Paper ML20209A155 Feedback Provided
ML20310A278
TerraPower-Type 1 Fuel Pin Qualification Plan White Paper ML21057A008 Feedback Provided
ML21147A548
ML21153A083
TerraPower, LLC - Natrium Decoupling Strategy White Paper ML22035A331 Cancelled
TerraPower, LLC, Submittal of Testing Programs White Paper ML22273A073 Feedback Provided
ML23074A347
TerraPower, LLC Topical Report, Regulatory Management of Natrium Nuclear Island and Energy Island Design Interfaces Topical Report ML22277A824 Feedback Provided
ML24011A321
Revised TerraPower, LLC Quality Assurance Topical Report, Revision 14 Topical Report ML22266A286 Feedback Provided
ML23220A295
ML23213A199
TerraPower, LLC, Regulatory Gap Analysis Report White Paper ML22266A285 Feedback Provided
ML23080A086
Principal Design Criteria for the Natrium Advanced Reactor Topical Report ML23024A281
ML24101A362		 Feedback Provided
ML24197A226
Fuel and Control Assembly Qualification Plan Topical Report ML23025A409 Feedback Provided
ML24220A154
Nascent Thermal Hydraulic Model White Paper White Paper ML23080A013 Feedback Provided
ML23229A541
Plume Exposure Pathway Emergency Planning Zone Methodology, Revision 1 Topical Report ML23080A045

ML23321A036		 Under Review
An Analysis of the Potential Volcanic Hazards at the Proposed Natrium Site Near Kemmerer, Wyoming Topical Report ML23115A387 Feedback Provided
ML24303A409
Human Factors Engineering Program Plan and Methodologies Topical Report ML23116A226 Under Review
Human Factors Engineering (HFE) Concept of Operations White Paper ML23125A328

ML24261B926		 Feedback Provided
ML23321A087
Preliminary Consensus Codes and Standards White Paper ML23130A413 Feedback Provided
ML23319A338
Radiological Source Term Methodology Report, Revision 1 Topical Report ML23223A235

ML24017A116

ML24261B944		 Feedback Provided ML25024A141
Design Basis Accident Methodology for In-Vessel Events without Radiological Release Topical Report ML23272A260

ML24295A202		 Feedback Provided ML24358A247
Radiological Release Consequences Methodology Topical Report ML23311A139

ML24208A181		 Feedback Provided ML25057A290
Reactor Stability Methodology Topical Report ML23334A239

ML24232A231		 Feedback Provided ML24324A227
Partial Flow Blockage Methodology Topical Report ML24085A822 Under Review
Design Basis Accident Methodology for Events With Release Topical Report ML24082A262

ML25063A329		 Under Review
Reactor Seismic Isolation System Qualification Topical Report ML24068A212 Under Review
Instrumentation and Control Architecture and Design Basis Topical Report ML24305A009

ML25036A030		 Feedback Provided

Page Last Reviewed/Updated Monday, April 14, 2025