Articles tagged with "reactor-safety"
Residents challenge drilling of US firm’s underground Gravity reactor
Residents of Parsons, Kansas, and local advocacy groups have raised significant concerns over Deep Fission’s underground “Gravity” nuclear reactor project, which recently began drilling site characterization. At a contentious community meeting, opponents, including the Prairie Dog Alliance, criticized changes in federal policy that they believe have weakened safety standards and reduced Nuclear Regulatory Commission (NRC) oversight. Many residents expressed apprehension about the project’s rapid timeline and potential long-term risks, urging a more cautious approach. Deep Fission representatives defended the reactor’s design, emphasizing its placement 6,000 feet underground to prevent traditional meltdown scenarios by balancing internal vessel pressure with external water pressure. They also described an innovative maintenance method involving pulling the reactor unit up via structural pipes for replacement without bringing it fully to the surface. The company clarified that the previously suggested pilot completion date of July 4, 2026, is outdated; instead, they anticipate grid connection and full project realization between 2027 and 2028 after a multi-year validation process
energynuclear-reactorunderground-reactorDeep-Fissionenergy-innovationnuclear-energyreactor-safetyWorld's most advanced supercomputers decode nuclear reactor turbulence
Researchers at Argonne National Laboratory are leveraging cutting-edge supercomputing power to improve nuclear reactor safety by accurately modeling turbulent fluid flow—a critical factor in heat transfer and gas mixing within reactors. Using advanced open-source computational fluid dynamics (CFD) tools, Nek5000 (CPU-based) and its GPU-optimized successor NekRS, the team can simulate complex turbulent behaviors, such as hydrogen gas mixing in containment structures, which is vital for preventing accidents like the 2011 Fukushima disaster. Their models demonstrated high accuracy in the international PANDA blind benchmark, successfully predicting gas flow patterns without prior experimental data. This breakthrough has attracted the attention of the U.S. Nuclear Regulatory Commission (NRC), which is collaborating with Argonne to apply these simulations for verifying complex containment geometries where traditional methods fall short. By transitioning simulations to the powerful Aurora supercomputer and integrating AI and machine learning through the DOE’s NEAMS program, Argonne aims to drastically reduce computation times and enhance predictive capabilities. This approach not only
energynuclear-energysupercomputingcomputational-fluid-dynamicsreactor-safetyturbulence-modelinghigh-performance-computingUS lab advances nuclear reactor safety with extreme 1,340°F testing
Researchers at the US Department of Energy’s Argonne National Laboratory have developed an advanced testing method capable of measuring the thermal conductivity of nuclear materials at temperatures up to 1,000 Kelvin (approximately 1,340°F). This breakthrough, based on the “suspended bridge method,” allows scientists to analyze microscopic samples of nuclear fuel—hundreds of times thinner than a human hair—in a vacuum environment. By isolating individual phases of fuel materials, the technique provides highly precise data on how heat moves through fuel under extreme conditions, which is critical for ensuring reactor safety and efficiency. The method currently operates across a wide temperature range (-450°F to 260°F) with imminent upgrades extending to 1,340°F, and initial tests on stainless steel and uranium-molybdenum alloys have validated its accuracy. This innovation addresses a significant gap in existing testing methods that struggle to capture how nuclear fuel degrades during actual reactor operations. By enabling precise measurement of thermal conductivity at extreme temperatures, the technique helps
energynuclear-energymaterials-sciencethermal-conductivityreactor-safetyadvanced-testing-methodsnuclear-fuelUS lab tests passive nuclear safety systems against insider threats
Engineers at the U.S. Department of Energy’s Argonne National Laboratory are proactively testing how insider threats could compromise passive safety systems in next-generation nuclear reactors before these designs are finalized and licensed. Passive safety systems, which rely on natural physical processes rather than active controls, are widely used and trusted in current reactors, but future designs like small modular reactors depend even more heavily on them. Argonne’s research focuses on realistic sabotage scenarios involving insiders with authorized access, such as leaving access points open or blocking cooling pathways, to identify vulnerabilities that could cause system failures. Using the Natural Convection Shutdown Heat Removal Test Facility, Argonne and collaborating national labs have simulated these sabotage scenarios to observe system responses under stress. Their findings, compiled in a report for the International Atomic Energy Agency, confirm that while multiple layers of protection—such as controlled access, alarms, and redundancy—make successful sabotage difficult, some vulnerabilities remain and should be addressed early in the design process. The goal is to guide reactor developers in strengthening
energynuclear-energypassive-safety-systemsreactor-safetyadvanced-nuclear-reactorsenergy-researchnuclear-securityHow Navy nuclear veterans maintain reactor safety that powers US energy innovation
US Navy nuclear veterans have transitioned from operating submarine reactors to managing the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL), one of the world’s most advanced neutron sources. HFIR, operated by the Department of Energy’s Office of Science in Tennessee, plays a critical role in producing isotopes for medical and industrial applications. The facility recently reached a milestone by being entirely staffed by graduates of the Navy’s Nuclear Propulsion Program, whose rigorous training and operational experience in naval reactors equip them to ensure HFIR’s safe and efficient operation. Candidates entering HFIR undergo a demanding multi-year training pipeline in the Navy, including academic coursework equivalent to two years of undergraduate STEM education and hands-on reactor operation. Many serve several years on naval vessels before transitioning to civilian roles at ORNL. The veterans bring not only technical expertise but also values of integrity, trust, and judgment essential for nuclear safety. While some face challenges due to lacking formal degrees, ORNL supports their advancement through education
energynuclear-reactorsUS-Navy-veteransHigh-Flux-Isotope-ReactorOak-Ridge-National-Laboratoryisotope-productionreactor-safetyNext-gen nuclear fuel from US firm gets green light for critical testing
US-based Lightbridge Corporation has reached a significant milestone in developing its next-generation nuclear fuel by completing the assembly of advanced fuel samples for critical irradiation testing. The proprietary fuel design uses an enriched uranium-zirconium metallic alloy, differing from the conventional ceramic uranium dioxide fuel used in most reactors. This metallic alloy is expected to improve heat transfer, allowing the fuel to operate at lower temperatures and thereby enhancing reactor safety margins. The assembled fuel samples are set for irradiation inside the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL), a key step toward gathering the empirical data needed for regulatory approval and commercial deployment. The preparation involved precise manufacturing and encapsulation of the fuel samples, conducted under a Cooperative Research and Development Agreement (CRADA) between Lightbridge and INL, exemplifying a public-private partnership to accelerate nuclear innovation. After irradiation in the ATR, the fuel will undergo detailed post-irradiation examination in shielded hot cells to assess structural changes and integrity. This testing aims to validate
nuclear-energyadvanced-nuclear-fueluranium-zirconium-alloyreactor-safetyirradiation-testingnuclear-materialsenergy-innovation2-metric-ton nuclear fuel boost planned under US-French collab
The article reports on a new US-French collaboration between Standard Nuclear Inc. and Framatome to form a joint venture, Standard Nuclear-Framatome (SNF), aimed at producing commercial-scale quantities of Tri-structural Isotropic (TRISO) nuclear fuel. TRISO fuel, known for its exceptional safety and durability at extreme temperatures, is ideal for advanced reactors such as small modular reactors (SMRs) and micro-reactors. The venture plans to begin manufacturing at Framatome’s Richland, Washington facility in 2027, pending regulatory approval from the U.S. Nuclear Regulatory Commission, with an initial production target of 2 metric tons of TRISO fuel annually. This represents a significant increase in capacity to support the growing advanced reactor market in the US and globally. The partnership leverages Standard Nuclear’s specialized manufacturing capabilities alongside Framatome’s extensive fuel cycle expertise and infrastructure, overseen by a joint board of directors. Both companies emphasize the strategic importance of establishing a robust domestic TR
energynuclear-fuelTRISOadvanced-reactorssmall-modular-reactorsnuclear-collaborationreactor-safetyNuclear reactor fears eased as US lab clears graphite of safety risk
Researchers at Oak Ridge National Laboratory (ORNL) have resolved a decades-old debate regarding the impact of microscopic pores in graphite used in nuclear reactors. Their study, published in the journal Carbon, confirms that the natural porosity within graphite blocks does not affect the material’s atomic vibrations or its fundamental neutron moderation properties. This finding is significant because graphite has been a key component in nuclear reactors since the first reactor in 1942, valued for its ability to withstand extreme temperatures and slow down neutrons to sustain controlled nuclear chain reactions. The research provides greater confidence in the safety and design of current and next-generation reactors, including very high-temperature reactors (VHTRs) and molten salt reactors. The study addressed a critical flaw in previous models that treated graphite porosity by randomly removing atoms, which artificially distorted the material’s vibrational properties and led to overestimations in reactor criticality calculations. Using advanced neutron scattering experiments combined with machine-learned atomic potentials, the ORNL team demonstrated that the increased neutron
energynuclear-reactorsgraphitematerials-scienceneutron-scatteringreactor-safetyhigh-temperature-reactorsUS to advance fusion reactor design to tackle heat, improve fuel
The U.S. Department of Energy (DOE) has launched four new collaborative projects under the Fusion Innovation Research Engine (FIRE) program to address critical challenges in fusion energy development. These projects—SWIFT-PFCs, BCTF, FILMS, and MiRACL—focus on advancing durable materials for reactor components, improving heat extraction and fuel breeding, and enhancing reactor safety. Oak Ridge National Laboratory (ORNL) plays a leading role in several initiatives, including developing plasma-facing materials for reactor walls and designing an integrated liquid metal cooling and fuel-breeding system. The BCTF project, led by ORNL, will build the Helium and Salt Technology Experiment (HASTE) facility to test prototype blanket and coolant systems, filling a gap in fusion research infrastructure. Additionally, the MiRACL project, led by Princeton Plasma Physics Laboratory (PPPL) with ORNL as a partner, aims to mitigate risks from sudden plasma confinement loss ("disruptions") through simulation and machine
fusion-energynuclear-reactorplasma-facing-materialsliquid-metal-coolingheat-extractionfuel-breedingreactor-safetyBreakthrough cladding tech promises longer life for US nuclear fuel
General Atomics Electromagnetic Systems (GA-EMS), a San Diego-based firm, has made a significant breakthrough in nuclear fuel cladding technology with its Silicon Carbide (SiC) composite material called SiGA. This multilayer composite cladding can withstand temperatures up to 3,452°F (1900°C), which is six times hotter than the conditions in current light-water, pressurized water reactors. The SiGA cladding features a patented localized SiC joining method that creates gas-tight, hermetic seals without exposing nuclear fuel pellets to high-temperature water, enhancing stability during temperature cycling and reducing manufacturing time. Fuel cladding serves as a critical barrier between nuclear fuel pellets and reactor coolant, ensuring safety and operational integrity. GA-EMS has demonstrated that its SiGA cladding exhibits superior high-temperature and irradiation resistance, verified through testing at Oak Ridge National Laboratory and Westinghouse’s reactor coolant test facility. After 180 days of exposure to corrosive water coolant, the SiC joints remained
energynuclear-energysilicon-carbidefuel-claddinghigh-temperature-materialsreactor-safetycomposite-materialsNew nuclear fuel in US blends thorium, uranium to cut waste, cost
US scientists at Idaho National Laboratory (INL), in partnership with Clean Core Thorium Energy and Texas A&M University, have developed and tested a novel nuclear fuel called ANEEL (Advanced Nuclear Energy for Enriched Life). This fuel blends thorium with high-assay low-enriched uranium (HALEU), enriched between 5% and 20% uranium-235, aiming to reduce nuclear waste, enhance reactor safety, and lower operational costs. Unlike typical fuels used in pressurized heavy-water reactors (PHWRs) that contain less than 0.72% uranium-235, ANEEL’s design is proliferation-resistant and can be used in existing PHWRs without requiring reactor or fuel bundle modifications. The ANEEL fuel pellets, fabricated with a proprietary thorium-uranium oxide blend featuring an annular shape for gas management, underwent months of irradiation testing at INL’s Advanced Test Reactor (ATR). Initial post-irradiation examinations revealed that the fuel maintained its structural
energynuclear-fuelthoriumuraniumadvanced-reactorsnuclear-waste-reductionreactor-safetyNext-gen nuclear reactors rely on solar salts for better heat control
energynuclear-reactorsthermal-energy-storagemolten-saltsadvanced-materialsradiation-resistancereactor-safety