This study contributes to investigation and better understanding of cladding (High Flux Isotope Reactor used to simulate the effects of high burnup on fuel cladding) materials performance in extended storage and transportation through the conduct of small scale and separate effects tests (SET).
Enginerred Barrier Systems (EBS) model evaluation and development is fundamental to the design and analysis of disposal concepts for generic repository systems; this report centers on progress made on modeling and experimental approaches to analyze physical and chemical interactions affecting clay barrier performance.
Experiments were used to examine water content in Permian salt samples including impact of variation in thermal regime on water content of evaporites and other mineral species, behavior of brine inclusions in salt, and evolution of the gas/liquid brine/salt system.
The Nuclear Science and Engineering Education Sourcebook is a repository of critial information on nuclear engineering programs at U.S. colleges and universities. It includes detailed information such as nuclear engineering enrollments, degrees, and faculty expertise. In this latest edition, science faculty and programs relevant to nuclear energy are also included.
The Reactor Materials element of the Nuclear Energy Enabling Technologies (NEET) program conducted its FY 2013 coordination meeting as a series of four web-conferences to act as a forum for the nuclear materials research community. The purpose of this meeting was to report on current and planned nuclear materials research, identify new areas of collaboration and promote greater coordination among the various Office of Nuclear Energy programs. The presentations from the webinar series are available here.
The Advanced Sensors and Instrumentation (ASI) element of the Nuclear Energy Enabling Technologies (NEET) program conducted its first Annual Project Review Meeting on May 21-22, 2013 in Germantown, Maryland. The purpose of this meeting was to review the status of the 10 ASI projects initiated in FY 2012. The meeting summary and project presentations are available here.
This work on the natural barrier system is conducted to reduce uncertainty in natural system performance and to fully exploit the credits that can be taken for the natural system barrier; several potential enhancements to describing barrier performance capabilities are presented.
The purpose of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Software Verification and Validation (V&V) Plan is to define what the NEAMS program expects in terms of V&V for the computational models that are developed under NEAMS.
Shale and clay-rich rock formations have been considered as potential host rocks for geological disposal of high-level radioactive waste throughout the world: modeling thermal, hydrological, mechanical, and chemical (THMC) of the near field of generic clay repository is discussed.
The Generic Deep Geologic Disposal Safety Case presents generic information that is of use in understanding potential deep geologic disposal options (e.g., salt, shale, granite, deep borehole) in the U.S. for used nuclear fuel (UNF) from reactors and high-level radioactive waste (HLW).
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.
The report summarizes available historic tests and the developed technical basis for disposal of heat-generating waste in salt, and the means by which a safety case for disposal of heat generating waste at a generic salt site can be initiated from the existing technical basis.
The 2013 Excess Uranium Inventory Management Plan describes a framework for the effective management of the Energy Department’s surplus uranium inventory in support of meeting its critical environmental cleanup and national security missions.
Results of testing employing surrogate instrumented rods (non-high-burnup, 17 x 17 PWR fuel assembly) to capture the response to the loadings experienced during normal conditions of transport indicate that strain- or stress-based failure of fuel rods seems unlikely; performance of high-burnup fuels continues to be assessed.
This report describes RD&D activities to support a safety case for disposal of heat generating radioactive waste (used nuclear fuel, high-level nuclear waste) in a generic bedded salt repository based on interactions from March, 2013 Workshop.
The Nuclear Energy Advanced Modeling and Simulation (NEAMS) quarterly report includes highlights, fuel and reactor product line accomplishments, recent and upcoming milestones, a technical spotlight on BISON fuel benchmarks, and a program spotlight on NE-KAMS.
This report evaluates existing capabilities at Idaho National Laboratory (INL) to determine if a practical and cost effective method could be developed for handling and opening full-sized dry storage casks in support of the U.S. Department of Energy's plan for confirmatory dry storage project for high burnup fuel.
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.
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.