Date Issued |
Topic |
Author Affiliation |
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 |