Date Issued |
Topic |
Author Affiliation |
10/2022 |
Seismically Isolated Nuclear Power Plants (Pre-Decisional Draft Regulatory Guide) |
NRC Staff |
10/2022 |
Technology-Inclusive, Risk-Informed, and Performance-Based Methodology for Seismic Design of Commercial Nuclear Plants (Pre-Decisional Draft Regulatory Guide) |
NRC Staff |
09/2022 |
Technology-Inclusive Identification of Licensing Events for Commercial Nuclear Plants (Draft Regulatory Guide) |
NRC Staff |
09/2022 |
Alternative Evaluation for Risk Insights (AERI) Methodology (Draft Regulatory Guide) |
NRC Staff |
09/2022 |
Operator Licensing Programs (Draft Interim Staff Guidance) |
NRC Staff |
09/2022 |
Guidance Augmenting NUREG-1791, “Guidance for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operator Staffing Requirements Specified in 10 CFR 50.54(m),” for Licensing Commercial Nuclear Plants under 10 CFR Part 53 (Draft Interim Staff Guidance) |
NRC Staff |
09/2022 |
Development of Scalable Human Factors Engineering Review Plans (Draft Interim Staff Guidance) |
NRC Staff |
03/2022 |
Nuclear Data Assessment for Advanced Reactors (NUREG/CR-7289) |
Oak Ridge National Laboratory |
03/2022 |
Fuel Qualification for Advanced Reactors (NUREG-2246)
|
NRC Staff |
12/2021 |
Final Draft: Micro-reactors Licensing Strategies |
NRC Staff |
11/2021 |
Ground Rules for Regulatory Feasibility of Remote Operations of Nuclear Power Plants |
NRC Staff |
10/2021 |
Final Report: Development of HFE Review Guidance for Advanced Reactors |
BNL/NRC staff |
07/2021 |
Fuel Qualification for Molten Salt Reactors Considerations (NUREG/CR-XXXX) |
Oak Ridge National Laboratory draft report |
05/2021 |
Corrosion in Sodium Fast Reactors |
Oak Ridge National Laboratory |
05/2021 |
An Overview of Non-LWR Vessel Cooling Systems for Passive Decay Heat Removal |
Argonne National Laboratory |
03/2021 |
Corrosion in Gas-Cooled Reactors |
Oak Ridge National Laboratory |
03/2021 |
Technical Assessment of Materials Compatibility in Molten Salt Reactors |
Oak Ridge National Laboratory |
02/2021 |
Design Review Guide (DRG): Instrumentation and Controls for Non-Light-Water Reactor (non-LWR) Reviews
|
NRC Staff |
01/29/21 |
Review of Operating Experience for Transportation of Fresh (Unirradiated) Advanced Reactor Fuel Types |
Center For Nuclear Waste Regulatory Analyses (CNWRA) |
01/29/21 |
Potential Challenges with Transportation of Fresh (Unirradiated) Advanced Reactor Fuel Types |
CNWRA |
01/29/21 |
Storage Experience with Spent (Irradiated) Advanced Reactor Fuel Types |
CNWRA |
01/29/21 |
Potential Challenges with Storage of Spent (Irradiated) Advanced Reactor Fuel Types |
CNWRA |
01/29/21 |
Transportation Experience and Potential Challenges with Transportation of Spent (Irradiated) Advanced Reactor Fuel Types |
CNWRA |
01/29/21 |
Disposal Options and Potential Challenges to Waste Packages and Waste Forms in Disposal of Spent (Irradiated) Advanced Reactor Fuel Types |
CNWRA |
01/29/21 |
Information Gaps and Potential Information Needs Associated with Transportation of Fresh (Unirradiated) Advanced Reactor Fuel Types |
CNWRA |
11/23/20 |
Topical Report EPRI-AR-1(NP)-A: EPRI Submittal, “Uranium Oxycarbide (UCO) Tristructural Isotropic (TRISO) Coated Particle Fuel Performance”
|
Electric Power Research Institute |
09/30/21 |
Relevant Advanced Reactor Benchmarks for Nuclear Data Assessment |
Oak Ridge National Laboratory |
09/15/20 |
Fuel Qualification for Advanced Reactors (Draft) |
NRC staff draft white paper |
09/30/20 |
Non-Light Water Reactor Fuel Cycle Environmental Data |
Pacific Northwest National Laboratory |
09/30/20 |
Environmental Impacts from Transportation of Fuel and Wastes to and from Non-Light Water Reactors |
Pacific Northwest National Laboratory |
09/09/20 |
Topical Report ANL/NE-16/17-NP-A: ANL Submittal, “Quality Assurance Program Plan for SFR Metallic Fuel Data Qualification”
|
Argonne National Laboratory |
07/31/20 |
Proposed Guidance for Preparing and Reviewing a Molten Salt Non-Power Reactor Application
- NRC letter dated November 18, 2020, "Endorsement of Appendix A to Oak Ridge National Laboratory Report, 'Proposed Guidance for Preparing and Reviewing a Molten Salt Non-Power Reactor Application,' as Guidance for Preparing Applications for the Licensing of Non-Power Liquid Fueled Molten Salt Reactors," ADAMS Accession No. ML20251A008.
|
Oak Ridge National Laboratory |
07/01/20 |
Molten Salt Reactor Fuel Salt Qualification Methodology |
Oak Ridge National Laboratory |
06/30/20 |
Key Nuclear Data Impacting Reactivity in Advanced Reactors |
Oak Ridge National Laboratory |
06/30/20 |
Technology-Inclusive Determination of Mechanistic Source Terms for Offsite Dose-Related Assessments for Advanced Nuclear Reactor Facilities |
Idaho National Laboratory |
06/30/20 |
Human Factors Considerations for Automating Microreactors |
Sandia National Laboratories |
05/31/20 |
Technical Letter Report on The Assessment of Tritium Detection and Control in Molten Salt Reactors: Final Report |
Argonne National Laboratory |
04/01/20 |
Technical and Licensing Considerations for Micro-Reactors |
Sandia National Laboratories |
03/31/20 |
Model Materials Controls and Accounting Plan for Pebble Bed Reactors |
Oak Ridge National Laboratory |
02/05/20 |
Regulatory Review of Micro-Reactors – Initial Considerations |
Brookhaven National Laboratory |
01/30/20 |
Simplified Approach for Scoping Assessment of Non-LWR Source Terms |
Sandia National Laboratories |
08/09/19 |
Hazards Associated with Molten Salt Reactor Fuel Processing Operations Presentation |
Oak Ridge National Laboratory |
08/07/19 |
Metal Fuel Fabrication Safety and Hazards Presentation |
Pacific Northwest National Laboratory |
06/30/19 |
Review of Hazards for Molten Salt Reactor Fuel Processing Operations |
Oak Ridge National Laboratory |
06/28/19 |
Metal Fuel Fabrication Safety and Hazards Final Report |
Pacific Northwest National Laboratory |
06/19/19 |
Advanced Reactor Siting Policy Considerations |
Oak Ridge National Laboratory |
06/10/19 |
NRC Regulatory History of Non-Light Water Reactors (1950-2019) |
Brookhaven National Laboratory |
03/31/19 |
Advanced Non-Light-Water Reactors Materials and Operational Experience |
NUMARK Associates |
03/31/19 |
Technical Gap Assessment for Materials and Component Integrity Issues for Molten Salt Reactors |
Oak Ridge National Laboratory |
11/30/18 |
Molten Salt Reactor Fuel Qualification Considerations and Challenges |
Oak Ridge National Laboratory |
08/21/18 |
Phenomena Important in Liquid Metal Reactor Simulations |
Brookhaven National Laboratory |
05/09/18 |
Phenomena Important in Modeling and Simulation of Molten Salt Reactors |
Brookhaven National Laboratory |