The purpose of the research effort is to determine the effects of canister and/or cask drying and storage on radial hydride precipitation in, and potential embrittlement of, high-burnup (HBU) pressurized water reactor cladding alloys during cooling for a range of storage temperatures and hoop stresses.
The objective of the Crystalline Disposal R&D Work Package is to advance our understanding of long-term disposal of used fuel in crystalline rocks and to develop necessary experimental and computational capabilities to evaluate various disposal concepts in such media. The major accomplishments are summarized in the report: 1) Development of Fuel Matrix Degradation Model (FMDM), 2) Thermal limit study of clay materials, 3) Short-term (< 35 days) study of uranium sorption and diffusion in bentonite, 4) Long-term (6 years) study of uranium diffusion in bentonite, 5) Colloid stability
The goal of work described in this document is to assess the effects of the manufacturing process on canister performance by evaluating the properties of a full-diameter cylindrical mockup of an interim storage canister. The mockup has been produced using the same manufacturing procedures as fielded spent nuclear fuel interim storage canisters. The document describes the design and procurement of the mockup and the planned characterization work; it provides status of the project and sample preparation for different analysis, and results of initial stress (and stress corrosion cracking, S
The Nuclear Energy Enabling Technologies Crosscutting Technology Development (NEET- CTD) Award Summaries describe the research achievements and planned accomplishments for ongoing projects under Reactor Materials, Advanced Sensors and Instrumentation, and Advanced Methods for Manufacturing sub-programs. These summaries will be updated annually, as needed.
The Advanced Sensors and Instrumentation (ASI) newsletter includes information about new developments and achievements in the area of sensors, instrumentation and related technologies across the Office of Nuclear Energy R&D programs.
The Advanced Methods for Manufacturing (AMM) newsletter includes information about selected projects pertaining to additive manufacturing, concrete technologies, and welding innovations currently funded by the Department of Energy’s Office of Nuclear Energy.
The Nuclear Energy Enabling Technologies (NEET) Advanced Sensors and Instrumentation (ASI) program, in coordination with the Office of Nuclear Reactor Technologies and the Office of Fuel Cycle Technologies, conducted an Instrumentations and Controls (I&C) project review webinar on September 16-18, 2014. The purpose of this webinar was to review the status of the I&C projects across the Office of Nuclear Energy and promote greater coordination among the various NE R&D programs.
The purpose of this agreement is to delineate the authorities and responsibilities of the Department of Energy (DOE) and the National Aeronautics and Space Administration (NASA) (the parties) in the research, technology development, design, production, delivery, space vehicle integration, and launch phases with respect to certain radioisotope power systems, including Radioisotope Thermoelectric Generators (RTGs) and Radioisotope Heater Units (RHUs), and to establish an agreement pursuant to which DOE and NASA will perform certain functions and provide funds for certain portions of the unde
The Administration has requested the restart of plutonium‐238 (Pu‐238) production in fiscal year (FY) 2011. The following joint start‐up plan, consistent with the President's request, has been developed collaboratively between the Department of Energy (DOE) and the National Aeronautics and Space Administration (NASA), and defines the roles and contributions of major users of Pu‐238 in response to Congressional request.
This report provides DOE’s plan to develop light water reactor (LWR) fuels with enhanced accident tolerance in response to 2012 Congressional direction and funding authorization. The result of the accident tolerant fuel development activities, if successful, will be a commercial product that is utilized in existing and future nuclear power plants.
The report provides a technically based gas sampling frequency strategy for the High-Burnup (HBU) Confirmatory Data Project. The evaluation of 1) the types and magnitudes of gases that could be present in the project cask, and 2) the degradation mechanisms that could change gas composition culminates in an adaptive gas sampling frequency strategy. The adaptive strategy is compared against the sampling frequency that has been developed based on operational considerations. Comparison evaluation of the Technically based and Operationally based sampling frequency strategies indicates there
Nuclear energy represents the single largest carbon-free baseload source of energy in the United States, accounting for nearly 20 percent of the electricity generated and over 60 percent of our low-carbon production. Worldwide, nuclear power generates 14 percent of global electricity. Continually increasing demand for clean energy both domestically and across the globe, combined with research designed to make nuclear power ever-safer and more cost-effective, will keep nuclear in the energy mix for the foreseeable future.
This study has evaluated the technical feasibility of direct disposal in a geologic repository, of commercial spent nuclear fuel (SNF) in dual-purpose canisters (DPCs) of existing designs. The investigation considered waste isolation safety, engineering feasibility, thermal management, and postclosure criticality control. The 3-year study concludes that direct disposal is technically feasible for most DPCs, depending on the repository host geology. Thermal management and postclosure criticality control are two important aspects of disposability, and both of these could be relatively sim
On May 1, 2015, the Secretary of Energy determined that continued uranium transfers for cleanup services at the Portsmouth Gaseous Diffusion Plant and for down-blending of highly-enriched uranium to low-enriched uranium will not have an adverse material impact on the domestic uranium mining, conversion, or enrichment industry (“2015 Secretarial Determination”). This Determination covers continued transfers at the rates specified in the Determination.
The document summarizes how a new round of staged thermal field testing will help to augment the safety case for disposal of heat generating nuclear waste in salt. The objectives of the proposed test plan are to: (1) address features, events, and processes (FEPs), (2) build scientific and public confidence, (3) foster international collaboration, (4) evaluate disposal concepts, and (5) validate coupled process models. The test proposal is designed to address long term performance assessment (PA) and shorter term operational uncertainties.
To address the challenges associated with pursuing commercial nuclear power plant operations beyond 60 years, the U.S. Department of Energy’s (DOE) Office of Nuclear Energy (NE) and the Electric Power Research Institute (EPRI) have established separate but complementary research and development programs: DOE-NE’s Light Water Reactor Sustainability (LWRS) Program and EPRI’s Long-Term Operations (LTO) Program. INL/EXT-12-24562 Revision 4
The Light Water Reactor Sustainability (LWRS) Program is a research and development (R&D) program sponsored by the U. S. Department of Energy (DOE), performed in close collaboration and cooperation with related industry R&D programs. INL/EXT-11-23452 Revision 3