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 | 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 ML25083A296 |
| Nascent Thermal Hydraulic Model White Paper | White Paper | ML23080A013 | Feedback Provided ML23229A541 |
| Plume Exposure Pathway Emergency Planning Zone Methodology, Revision 3 | Topical Report | ML23080A045 ML23321A036 ML24303A147 ML24304B034 |
Feedback Provided ML25065A250 |
| 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 ML24261B925 |
Feedback Provided ML25085A268 |
| 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 ML25063A323 |
| Design Basis Accident Methodology for In-Vessel Events without Radiological Release | Topical Report | ML23272A260 ML24295A202 |
Feedback Provided ML25106A040 |
| Radiological Release Consequences Methodology | Topical Report | ML23311A139 ML24208A181 |
Feedback Provided ML25057A290 |
| Reactor Stability Methodology | Topical Report | ML23334A239 ML24232A231 |
Feedback Provided ML25105A066 |
| Partial Flow Blockage Methodology | Topical Report | ML24085A822 ML25129A064 |
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 ML24068A186 |
Feedback Provided ML25036A030 |
Page Last Reviewed/Updated Tuesday, July 29, 2025
Page Last Reviewed/Updated Tuesday, July 29, 2025