Factsheet about DOE High Burnup Research Cask Project (HBURC) dated April 2025.
This report fulfills the M3 milestone M3SF-23PN0203020614, “Updated NPP Site Evaluation Report (2).” This report is an update of the 2021 report Nuclear Power Plant Infrastructure Evaluations for Removal of Spent Nuclear Fuel and includes expansion of the site evaluations to include operating nuclear power plant (NPP) sites and to incorporate updated site inventory data. Figures that include the number of spent nuclear fuel (SNF) assemblies and metric tons heavy metal (MTHM) in a single figure have also been added to the report.
Consent-based siting consortia support DOE's efforts to facilitate inclusive community engagement and elicit public feedback on consent-based siting, management of spent nuclear fuel, and federal consolidated interim storage. The 12 awardees are comprised of various organizations to help reach communities across the country and remove barriers to participate in DOE's consent-based siting process.
Awardees have made significant progress in carrying out community engagement activities and providing direct grants to communities wanting to learn more.
The U.S. Department of Energy (DOE) has established a Tribal Collaboration Initiative (TCI) that will ensure federally recognized Tribes have direct and meaningful input into DOE’s consent-based siting (CBS) process for one or more federal consolidated interim storage facilities (CISFs). Establishing a TCI ensures federally recognized Tribal interests and concerns are directly communicated and accurately represented to DOE, as the agency continues developing the siting process.
This node contains the segmented nuclear power plant site evaluation report. It consists of a main report and 20 supplements that contain the site evaluations for the following sites:
Consent-based siting consortia support DOE's efforts to facilitate inclusive community engagement and elicit public feedback on consent-based siting, management of spent nuclear fuel, and federal consolidated interim storage. The 12 awardees are comprised of various organizations to help reach communities across the country and remove barriers to participate in DOE's consent-based siting process.
Awardees have made significant progress in carrying out community engagement activities and providing direct grants to communities wanting to learn more.
Consent-based siting consortia support DOE's efforts to facilitate inclusive community engagement and elicit public feedback on consent-based siting, management of spent nuclear fuel, and federal consolidated interim storage. The 12 awardees are comprised of various organizations to help reach communities across the country and remove barriers to participate in DOE's consent-based siting process.
Awardees have made significant progress in carrying out community engagement activities and providing direct grants to communities wanting to learn more.
This is the information sheet for Spent Nuclear Fuel Package Performance Demonstration (PPD).
This is an information poster for PPD stakeholders.
This is a PPD poster with information for Tribes
Mothers for Nuclear Informational Flyer
Understanding DOE’s Critical Decision Process: Progress Toward a Consolidated Interim Storage Facility for Commercial Spent Nuclear Fuel
The critical decision (CD) process is used by the Department of Energy (DOE) to manage the Department’s large-scale, long-term projects, also known as capital projects. CD-0 was recently approved for DOE’s Consolidated Interim Storage Facility project. Learn more about this milestone.
What is Consent-Based Siting?
Consent-based siting is an approach to siting facilities that prioritizes the participation and needs of people and communities and seeks their willing and informed consent to accept a project in their community. The U.S. Department of Energy (DOE) is using a consent-based siting approach to identify one or more sites for federal consolidated interim storage facilities for commercial spent nuclear fuel.
The preclosure criticality analysis process described in this technical report provides a systematic approach for determining the need for criticality controls and for evaluating their effectiveness during the preclosure period of the Monitored Geologic Repository at Yucca Mountain, Nevada.
The Monitored Geologic Repository (MGR) Waste Package Operations (WPO) of the Civilian Radioactive Waste Management System Management and Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of Pu-ceramic waste forms. The Pu- ceramic (Refs. 1 and 2) is designed to immobilize excess plutonium from weapons production, and has been considered for disposal at the potential Yucca Mountain site.
The purpose of this calculation is to document the LaSalle Unit 1 boiling water reactor (BWR) fuel depletion calculations performed as part of the commercial reactor critical (CRC) evaluation program. The CRC evaluations constitute benchmark calculations that support the development and validation of the neutronics models used for criticality analyses involving commercial spent nuclear fuel in a geologic repository. This calculation incorporates control blade effects and minor variations in the SAS2H assembly modeling.
The purpose of this calculation is to apply the process described in the TDR-DS0-NU-000001 Rev. 02, Preclosure Criticality Analysis Process Report (Ref. 2.2.25) to aid in establishing design and operational criteria important to criticality safety and to identify potential control parameters and their limits important to the criticality safety of commercial spent nuclear fuel (CSNF) handling operations in the Wet Handling Facility (WHF)
This analysis provides information necessary for total system performance assessment (TSPA) for the license application (LA) to include the excess U.S. Department of Energy (DOE) plutonium in the form of mixed oxide (MOX) spent nuclear fuel and lanthanide borosilicate (LaBS) glass. This information includes the additional radionuclide inventory due to MOX spent nuclear fuel and LaBS glass and the analysis that shows that the TSPA models for commercial spent nuclear fuel (CSNF) and high-level waste (HLW) degradation are appropriate for MOX spent nuclear fuel and LaBS glass, respectively.
The purpose of this scientific analysis is to document the results and interpretations of field experiments that test and validate conceptual flow and radionuclide transport models in the saturated zone (SZ) near Yucca Mountain, Nevada. The test interpretations provide estimates of flow and transport parameters used in the development of parameter distributions for total system performance assessment (TSPA) calculations.
The purpose of this calculation is to document the McGuire Unit 1 pressurized water reactor (PWR) reactivity calculations performed as part of the commercial reactor critical (CRC) evaluation program. CRC evaluation reactivity calculations are performed at a number of statepoints, representing reactor start-up critical conditions at either beginning of life (BOL), beginning of cycle (BOC), or mid-cycle when the reactor resumed operation after a shutdown.
