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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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At least 1,711 records · Page 95
All sourcesNASA NTRSDOE OSTI
DOE OSTI2025

Latest Results from the ICARUS Experiment at the SBN Program

The ICARUS Collaboration is now entering its fifth year of continuing operations of the 760-ton liquid argon T600 detector. The T600 was overhauled at CERN after operations at the LNGS underground laboratory in Italy and moved to its present location at FNAL - as part of the Short-Baseline Neutrino (SBN) program - where it successfully completed its commissioning phase in June 2022. At FNAL ICARUS collects neutrino interactions from both the Booster Neutrino Beam (BNB) and off-axis from the Main Injector Neutrino beam (NuMI). To date, ICARUS has accumulated approximately $7.5\cdot 10^20$ protons on target (POT) with the BNB and about $6.2\cdot 10^20$ POT with NuMI. Within the SBN program ICARUS will search for evidence of short-baseline oscillations, potentially explained by eV-scale sterile neutrinos, jointly with the Short-Baseline Near Detector (SBND). In addition, ICARUS is performing stand-along oscillation searches in disappearance mode and measuring neutrino cross sections on argon with both the BNB and NuMI beams. It is also performing searches for additional Beyond the Standard Model signatures. Preliminary results from the ICARUS experiment, using data from the BNB and NuMI neutrino beams, will be presented.

Ricci, Alessandro Maria [U. Pisa (main); INFN, Pis↗
DOE OSTI2025

IOTA Bake System

The IOTA ring is vital to the advancement of accelerator sciences, and a large part of its attractiveness to accelerator physicists is its modularity and the versatility that this function provides. Up until this point, the FAST accelerator has provided electron beam for the studies in IOTA. With the soon to be commissioned IOTA Proton Injector in lieu, the requirement for better vacuum to support future proton studies in the ring have arrived. Our solution is the IOTA Bake System which has the goal of facilitating this requirement.

Thompson, Travante [Fermilab]↗
DOE OSTI2025

Novel Technology of Non-Contact Real-Time Radiation Damage Sensor for High Power Targets

High-power proton beams planned for forthcoming long-baseline neutrino experiments will subject solid targets to unprecedented radiation damage, threatening reliability and increasing costs. To address this challenge, we are building a real-time, non-contact sensor that tracks damage by measuring broadband laser reflectivity changes from the target surface. A low-power super-continuum Class 3B laser illuminates the sample inside a vacuum test chamber while a high-resolution fiber-coupled spectrometer captures S- and P-polarized light; spectral shifts reveal defect-driven variations in optical constants. My internship goal is to design, build, and commission this prototype by implementing a laser-safety interlock and light shield, integrating remote-operation cameras, and fabricating modular 3-D-printed mounts that enable tool-free swaps without disturbing alignment. The laser, spectrometer, and vacuum chamber have been delivered; interlock hardware, cameras, and mounts are in final assembly, and leak testing of the chamber is underway. Upcoming work will focus on initial calibration of the sensor and executing first beam-irradiation studies.

Pumarino, Rafael↗
DOE OSTI2025

Microreactor Incident-Free Transportation Radiation Dose Assessment

This report, prepared by Pacific Northwest National Laboratory (PNNL) for the U.S. Nuclear Regulatory Commission, provides an estimate of the radiation dose related to the transportation of microreactors following the regulatory limits established in Title 10 of the Code of Federal Regulations (10 CFR) 71.47(b). The transportation of irradiated microreactors poses unique challenges. Microreactors may be challenged to meet the current 10 mrem/hr limit at 2 meters from the vehicle in 10 CFR 71.47(b). The need to modify packaging to be within practical weight and size limits for shipping may limit the amount of shielding that can be applied for a microreactor transportation package design. Operational strategies that would necessitate moving a reactor within a short time after its operating life may result in higher radiation dose rates associated with lower cooling times. This study estimates the radiation dose to maximally exposed individuals (MEIs) under the current regulatory radiation level limit of 10 mrem/hr at 2 meters from the vehicle as well as alternative limits of 10, 50, 100, and 200 mrem/hr at 2 meters from the vehicle. This analysis expands on prior incident free transportation radiation dose assessments conducted for spent nuclear fuel (SNF) and radioactive waste transportation. The key factors analyzed include the microreactor fuel type and burnup, shipment cooling periods, shielding designs integrated into transport packaging, and exposure scenarios for MEIs for highway and rail transport. This report considers additional distances that may be associated with compensatory measures to ensure safe transport conditions under varying radiation dose limits, including enhanced routing measures, escort protocols, vehicle inspections, and operational restrictions.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2025

U.S. Department of Energy Office of Legacy Management 2024 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

This report, in fulfillment of a U.S. Nuclear Regulatory Commission (NRC) license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) in 2024. These activities occurred at the 19 uranium mill tailings disposal sites established under Title I of the Uranium Mill Tailings Radiation Control Act (UMTRCA) and verify that the UMTRCA Title I disposal sites remain in compliance with license requirements and Long-Term Surveillance Plans (LTSPs). Individual chapters for each site are available on the LM public website at https://energy.gov/lm/sites/lm-sites.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2026

Local Resource Assessment: Beetle-Killed Spruce in Alaska

This report synthesizes forest inventory and spatial data from federal and state sources to present a snapshot of beetle-killed spruce across Southcentral and Interior Alaska. This natural resource is under investigation for use in cellulose-based products, particularly building insulation. Research funded by the Department of Energy's ARPA-E program, has successfully developed insulation - Celium - using beetle-killed spruce combined with mycelium, the root network of fungi. The resulting insulation product can be manufactured locally and used across all Alaskan climate zones for residential, commercial, and shipping applications. Removing standing dead wood also contributes to wildfire risk reduction and mitigates associated public health impacts. This Local Resource Assessment, funded by the Denali Commission, contextualizes and reconciles unaligned forestry data sources, establishing a pathway to refined, replicable analysis and, ultimately, presenting estimates of beetle-killed spruce biomass to inform the potential scale and development of a Celium industry.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗
DOE OSTI2026

Design and Development of the Handling Frame Assembly Table for the National Ignition Facility Blast Shields

The Handling Frame Assembly Table is a custom designed piece of equipment developed to support the NIF Sustainment Project. The goal of the NIF Sustainment Project is to refurbish the National Ignition Facility (NIF), the world’s largest and most energetic laser, so it can continue advancing research in fusion energy, national security, and high energy density physics. A key aspect of this effort involves replacing all 1,728 blast shields on the NIF, which requires specialized equipment such as the Handling Frame Assembly Table to support the production of new blast shields. This project follows a systems engineering approach that guides the design sequence. This report documents the design process from initial concept through final design, including stakeholder analysis, requirements development, conceptual design, final design, and design validation. Future work will focus on building and commissioning the system.

42 ENGINEERING↗
DOE OSTI2026

Considerations and Mitigations for Liquid Metal Target Campaigns in the Material Plasma Exposure eXperiment

This document reports a detailed initial risk assessment associated with the exposure of liquid metal (LM) targets to plasma flux in the Material Plasma Exposure eXperiment (MPEX) at ORNL. This document, while preliminary, does give a comprehensive mitigation plan to the risks along with justification and recommendations before potentially proceeding to LM exposures. At the date of issuance of this report, the MPEX Project has completed Final Design, and the MPEX device is in the Fabrication stage. Remaining project stages include Commissioning of the device with plasma and transitioning to routine Operations for research. As will be described in this document, since the MPEX device is currently being fabricated and the existing design does not include sufficient engineering provisions for most LM targets, no LM exposures will be conducted in MPEX until further assessment can be conducted and the necessary engineering changes incorporated (during MPEX Operations.)

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
DOE OSTI2026

Siting Analyses for Advanced Nuclear Advisors (Final CRADA Report)

This report summarizes siting evaluation assistance provided to Advanced Nuclear Advisors (ANA) under CRADA/NFE-25-10693 for suitability of advanced nuclear technologies to meet siting criteria from the Nuclear Regulatory Commission (NRC) and associated guidance documents including the Electric Power Research Institute (EPRI) siting guide and other proprietary datasets. Advanced Nuclear Advisors provided sites for reactor siting evaluations using the Oak Ridge – Siting Analysis for power Generation Expansion (OR-SAGE) tool. Individual data packages for each site are provided separately.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2024

Variable Transmission Line Ratings

This paper outlines the concept of variable-transmission facility ratings. This topic is of heightened importance following the recent Federal Energy Regulatory Commission (FERC) Order No. 881 which requires the implementation of ambient adjusted ratings (AARs) for FERC jurisdictional portions of the transmission system. Additionally, FERC issued an Advanced Notice of Proposed Rulemaking (ANOPR) implying a future order on Dynamic Line Rating (DLR) requirements. The various types of facility-rating methodologies will be discussed with a focus on how they can benefit the stability, capacity, and reliability of the grid.

24 - POWER TRANSMISSION AND DISTRIBUTION↗
DOE OSTI2025

FNCL Enhancements Implementation (FY25 Annual Report)

The FNCL investigations team at Lawrence Livermore National Laboratory (LLNL) has completed research and development of hardware, signal processing, and analysis tools to enhance the measurement capabilities of both the current CAEN SyS VeryFuel Fast Neutron Collar (FNCL) instrument and a next-generation FNCL prototype. The team successfully built and commissioned the LLNL Demonstrator System: a fully integrated, three-panel detector system featuring higher segmentation, plastic scintillators (EJ-276D), Silicon Photomultipliers (SiPMs), no high-voltage requirement, a reduced electronic footprint, and the LLNL-developed Gaussian Mixture Model Pulse Shape Discrimination (GMM-PSD) signal processing. An extensive experimental campaign was conducted at LLNL’s Inherently Safe Subcritical Assembly (ISSA) facility using both the baseline FNCL and the LLNL Demonstrator. The campaign results validated system performance, calibration stability, and the effectiveness of advanced signal processing and analysis algorithms in a relevant environment.

and physical protection↗
DOE OSTI2026

Virtual Power Plant Architecture and Resilient Design

Virtual Power Plants (VPPs) represent a fundamental shift in electric grid operations, aggregating distributed energy resources (DERs) such as solar panels and battery storage to deliver utility-scale grid services traditionally provided by centralized power plants. This report examines the unique architectural, operational, and digital assurance considerations that distinguish VPPs from conventional utility infrastructure as they scale from pilot projects to mainstream deployment across the United States. While VPPs offer significant opportunities for grid modernization and enhanced flexibility, their distributed, multi-stakeholder architecture introduces distinct security challenges that differ fundamentally from traditional generation facilities. The analysis identifies risks in VPP operations, including device-level security gaps, platform vulnerabilities, and communication protocol weaknesses that create expanded attack surfaces compared to centralized power plants. Through examination of real-world incidents and emerging threat patterns, the report demonstrates how some VPPs' reliance on consumer-owned devices, public internet infrastructure, and complex vendor ecosystems require new approaches to digital assurance and operational security. The findings provide practical guidance for utilities, regulators, and aggregators to implement robust security frameworks and operational best practices essential for maintaining grid reliability as VPP deployment accelerates under the Federal Energy Regulatory Commission (FERC) Order 2222 and related regulatory initiatives.

24 - POWER TRANSMISSION AND DISTRIBUTION↗
DOE OSTI2022

Cyclotron Road Partnership (CRADA Final Report)

The Cyclotron Road program was launched in 2015 by LBNL, with support from the DOE Advanced Manufacturing Office (AMO), to accelerate technical innovation in the energy sector. The program brought scientist-entrepreneurs to LBNL to access unique research assets and expertise. In 2016, LBNL partnered with Activate Global, Inc., a 501(c)(3) non-profit, to expand the program and provide enhanced access to capital and business support services. Under this Cooperative Research and Development Agreement (CRADA), LBNL provided technical support and expertise, while Activate engaged with private sector, philanthropic, and government partners to support innovators and research-phase small businesses, aiming to translate high-impact materials and manufacturing technologies from lab to market. The program received funding from various sponsors, including the DOE, DARPA, and the California Energy Commission, and was managed through a collaborative framework that maintained accountability by the participant organization and Berkeley Lab regarding roles and tasks relevant to this collaboration.

99 GENERAL AND MISCELLANEOUS↗
DOE OSTI2026

Dose Measurement and Monte Carlo FLUKA simulations for the FE and FOE of the 27-ID HEX Beamline

The 27-ID High Energy Engineering X-ray Scattering (HEX) beamline, commissioned in 2024, operates within the Hard X-ray Scattering and Spectroscopy program at Brookhaven Lab’s National Synchrotron Light Source II (NSLS-II). The high energy spectrum at the HEX beamline extends up to several hundred keV, making it well suited for applications such as imaging large engineering samples, including fully assembled batteries, fuel cells, etc.

43 PARTICLE ACCELERATORS↗
DOE OSTI2026

Updated General Aviation Non-Airport Crash Density Values Using Data Obtained from the U.S. National Transportation Safety Board for 2000 through 2019

This report documents the calculation of the General Aviation (GA) non-airport crash density for Department of Energy (DOE) sites and power generating facilities licensed by the Nuclear Regulatory Commission (NRC) using the methodology outlined in DOE-STD-3014-2006, Accident Analysis for Aircraft Crash Into Hazardous Facilities. The results of this report will be used by the American Nuclear Society (ANS) for the development of ANS standard 2.36, Accident Analysis for Aircraft Crash into Reactor and Nonreactor Nuclear Facilities.

99 GENERAL AND MISCELLANEOUS↗
DOE OSTI2026

Report on the Update and Codification of Expert Knowledge into ASTM Standard Practice E521

The overall purpose of the Grand Challenge Integrated Research Project (IRP), Accelerating the Qualification of Materials to Enable Rapid Deployment of Advanced Reactors, is to fulfill several objectives. The first objective is to complete and demonstrate/establish the process for predicting the microstructure and properties of structural materials in reactor and at high doses using ion irradiation as an accurate predictive tool for assessing behavior under reactor irradiation. The second objective is for this process to be adopted as part of an ASTM standard, and to work with the US Nuclear Regulatory Commission to utilize this standard in licensing decisions on advanced reactor designs for which such data are nonexistent or impractical to achieve. The need for standardized procedures is apparent based on the outcomes of a recent round-robin experiment from laboratories using ion beams for radiation damage studies and the roadmap for ion beam technologies to address challenges for the advancement of nuclear energy technologies.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2026

FY26 Mid-Year Report

The goal of this project is to develop specific aspects of ultra-high-resolution microcalorimeter technologies that support IAEA Nuclear Material Laboratory needs and the goals of SP-1 19/NML-003 "Microcalorimetry Analysis Technique for NML" but are outside the scope of the SP-1. The focus is on commissioning, assembly, and testing of the microcalorimeter decay energy spectrometer with superconducting transition-edge sensors (TESs) and magnetic microcalorimeters (MMCs) in preparation for transfer to the IAEA Nuclear Material Laboratory.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗