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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 703 records · Page 39
All sourcesNASA NTRSDOE OSTI
DOE OSTI2025

Conjugate Heat Transfer Modeling of Salt-Filled Fuel Pins for Stable Salt Reactor Safety Analysis

The Stable Salt Reactor (SSR) combines the proven structural design of light water reactor fuel assemblies with the inherent safety and fuel-cycle advantages of molten salt technology. In its fast reactor configuration, the SSR utilizes recycled nuclear waste as fuel, sealed within narrow salt-filled fuel pins and cooled by a surrounding liquid salt coolant. Reliable transfer of heat from the molten fuel salt through the cladding to the external coolant is essential for both reactor safety and performance. This work investigates conjugate heat transfer (CHT) in the SSR’s salt-filled fuel pins using NekRS, a high-fidelity spectral element computational fluid dynamics (CFD) solver. The analyses capture internal natural convection within the molten fuel salt and external forced convection in the coolant, under steady-state and transient operating conditions. Parametric studies evaluate how variations in reactor power and coolant flow rate influence heat transfer distributions and system response. The high-fidelity CFD results are time-averaged and post-processed for direct comparison with moderate-fidelity Reynolds-averaged Navier–Stokes (RANS) models, and for the development of reduced-order models within the SAM system code. These validated models support fast-running safety analyses of normal and off-normal transients, improving predictive capability for key safety margins. By integrating advanced CFD with system-level safety tools, this study strengthens the modeling framework for SSR design, reduces uncertainty in molten salt CHT simulations, and accelerates the engineering and licensing of next-generation nuclear reactors.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2017

Influence of cut layer on cutting

The contact of the chip with the tool’s front surface in cutting is analyzed by numerical modeling. The high-pressure zones and buildup at the tool’s contact surface are studied. The influence of plastic instability of the chip surface and vortex deformation modes on tool wear is considered.

42 ENGINEERING↗
DOE OSTI2018

Influence of the Vapor Channel in Deep Laser Welding

The physical processes associated with deep welding are analyzed. A two-dimensional numerical model is proposed for the interaction of the laser beam with the medium in the vapor channel. The following processes are considered: heat and mass transfer; absorption and reradiation of the beam’s energy by the plasma; interaction of the plasma with the channel walls; and heat transfer to the cold sample. The model establishes a quantitative relation between the welding conditions and the results of butt welding. That decreases the expenditures in the development of laser-welding processes.

42 ENGINEERING↗
DOE OSTI2023

Ducted Fuel Injection Provides Consistently Lower Soot Emissions in Sweep to Full-Load Conditions

Earlier studies have proven how ducted fuel injection (DFI) substantially reduces soot for low- and mid-load conditions in heavy-duty engines, without significant adverse effects on other emissions. Nevertheless, no comprehensive DFI study exists showing soot reductions at high- and full-load conditions. This study investigated DFI in a single-cylinder, 1.7-L, optical engine from low- to full-load conditions with a low-net-carbon fuel consisting of 80% renewable diesel and 20% biodiesel. Over the tested load range, DFI reduced engine-out soot by 38.1–63.1% compared to conventional diesel combustion (CDC). This soot reduction occurred without significant detrimental effects on other emission types. Thus, DFI reduced the severity of the soot–NO x tradeoff at all tested conditions. While DFI delivered considerable soot reductions in thepresent study, previous DFI studies at low- and mid-load conditions delivered larger soot reductions (>90%) compared to CDC operation at the same conditions. Therefore, the DFI configuration used here has been deemed nonoptimal (in terms of parameters such as the injector-spray and piston geometries), and several improvements are recommended for future studies with high-load DFI. Further, these improvements include employing better spray-duct alignment, a deeper piston bowl with a smaller injector umbrella angle, and a fuel injector that opens and closes faster. The study also suggests future research to make DFI ready for commercialization, such as metal-engine tests to ensure desirable DFI performance over an engine’s complete speed/load map. Overall, this study supports the continued development and commercialization of DFI to meet upcoming emissions regulations for heavy-duty vehicles. Specifically, multicylinder engine experiments and CFD simulations should be utilized to optimize the performance and clarify the full potential of DFI.

33 ADVANCED PROPULSION SYSTEMS↗
DOE OSTI2016

Design of a low-cost, compact SRF accelerator for flue gas and wastewater treatment

Funding is being requested pursuant to a proposal that was submitted and reviewed through the Portfolio Analysis and Management System (PAMS). PAMS Proposal ID: 222439. The proposed project consists of the design of a novel superconducting continuous-wave accelerator capable of providing a beam current of ~1 A at an energy of 1-2 MeV for the treatment of flue gases and wastewater streams. The novel approach consists on studying the feasibility of using a single-cell Nb cavity coated with a thin Nb3Sn layer of the inner surface and conductively cooled by to 4.2 K by cryocoolers inside a compact cryomodule. The proposed study will include beam transport simulations, thermal and mechanical engineering analysis of the cryomodule and a cost analysis for both the fabrications costs and the operational and maintenance costs of such accelerator. The outcome of the project will be a report summarizing the analysis and results from the design study.

99 GENERAL AND MISCELLANEOUS↗
DOE OSTI2022

Technology Enablers for Advanced Gasoline Compression Ignition Engines

To meet current emission regulations and increasingly demanding global fleet CO2 standards on fuel economy and future trends towards life cycle GHG emissions, advanced combustion engines remain significant in the passenger vehicle sector to achieve high efficiency and low emissions over the full operating range. Lean burn gasoline compression ignition (GCI) technology has shown to have the most potential in reaching these goals, although it faces challenges in the operating range. In this study, an advanced GCI engine is considered with the capability to operate under two combustion modes, namely low temperature combustion (LTC) and GCI. They are enabled with the use of two Hyundai in-house developed technologies; an advanced valve control mechanism known as continuously variable valve duration (CVVD) and a high-pressure gasoline injection system. At low load, the engine utilizes dual CVVD and dual CVVT (continuously variable valve timing) mechanisms for both intake and exhaust valvetrains to enable NVO (negative valve overlap) to trap hot residuals. The hot residuals enable low load auto-ignition, and the phasing control of that auto-ignition is achieved by varying the degrees of NVO, and in turn, the amount of hot residuals. This is done in real time with respect to the changes in engine loads or operating conditions, significantly improving cylinder-phasing control in LTC mode, and subsequently is able to realize a fuel economy gain and reduced emission benefits. Early direct injection during NVO or intake stroke is used to form homogenous or quasi-homogenous air-fuel mixture for LTC. At mid to high loads, late direct injection of gasoline or GCI mode is employed to take advantage of the high volatility and high resistance to auto-ignition of gasoline fuel, so that diesel-engine like high combustion efficiency can be achieved with lower soot emissions for the same NOx level as diesel combustion. In this paper, the key control and fueling technologies that enable this multiple mode combustion are introduced, and the resultant analysis on engine test and CFD simulation at LTC and GCI operating conditions are presented in detail.

Gasoline compression ignition, low temperature com↗
DOE OSTI2017

Which parameters might help to predict an impact on reactivity for mixed fissile units in a storage array?

Several studies have already been performed on mixed fissile units in storage arrays and concluded that the neutron spectrum of the fissile material, the shape of fissile units, the interstitial moderation and structural materials may have an impact on reactivity. For this paper, calculations are performed on a simplified infinite planar array with one level of fissile material units axially reflected by concrete. Fissile material is modelled by a cylinder shape centered in the array mesh selected (120 cm height and 60 cm pitch). Either air or interstitial moderation by water is modelled between the fissile units. Three parameters are studied: the fissile materials (with various moderation conditions), the cylinder dimension and the nature of the structural material. The main following conclusions can be drawn from these calculations. First, for several mixed-array cases, air-spaced mixed arrays present a high increase on reactivity whereas interstitial moderation between fissile units leads to no or little impact. Secondly, fissile unit shapes do not explain directly the mixing impact on reactivity. Thirdly, structural materials have an important impact on reactivity in mixed array (either an increase or a decrease) due to their absorbing and/or moderating properties either when air or interstitial moderation are modelled between fissile units. Fourthly, no simple parameter was found to predict the impact on reactivity of mixed array in all studied configurations. However, a comparison of different neutron spectrum parameters can help to predict the absence or potential presence of a 'mixing effect'. Indeed, if all parameters are similar, no 'mixing effect' is observed. But, if these parameters present differences, there might be a 'mixing effect'. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2020

Virtual/Augmented Reality (VR/AR):Tools for Nuclear Training, Operations and Design

Introduction: Problems: Mistakes in the field due to a lack of information (Ex: Pump repair failure rate 50%); Avoidable exposure due to multiple employees for procedure adherence and monitoring; Debates over 2D drawings can be more easily resolved. Purpose: Training: Employees can be trained more effectively. Operating: Operations can be carried out more efficiently with fewer workers required with AR. Design Review: Pull the designers and designs into VR. Design: VR: Unreal Engine, Unity, Custom. AR: HoloLens: Unity, Custom - DirectX 12.

42 ENGINEERING↗
DOE OSTI2016

Modeling and analysis of an AMB system with flexible rotor in HTR-10GT - 18550

Active magnetic bearing (AMB) has been widely used in high-temperature gas-cooled reactor (HTR) for its specific properties: free of contact, absence of lubrication, capability of rotating at high speed. AMB system is inherently unstable since positive feedback exists in the open loop system and, thus, requires feedback control. From the control view of point, accurate system model is essential for designing of an effective controller especially when the flexible gyroscopic rotor is involved. In the paper, a flexible rotor and an open-loop AMB system model were established for the purpose of controller design. Dynamic characteristics of the undamped flexible rotor are analyzed including modal vibration analysis and undamped natural frequencies. Additionally, some characteristics of open-loop AMB system are investigated such as relationship between support stiffness and natural frequencies, and the system frequency response. The analysis results in this paper will provide valuable information for AMB system feedback controller design. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

Assessment of the Cobra-TF Post-CHF Models using FEBA Experimental Data

The reduction of the conservationism through a high fidelity description of the physics to achieve more reliable safety related analyses has a growing importance in the nuclear industry. The new tools require using multi-physic coupled codes at refined scales such a CFD or sub-channel codes. In the framework of the development activities of the 3D thermal-hydraulics sub-channel code CobraTF (CTF), Tractebel ENGIE together with the Karslruhe Institute of Technology (KIT) participate actively in the users' group identifying possible working areas on the code. (authors)

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2017

Deterministic Selection of Design Extension Condition without Core Melt

The concept of beyond design basis accidents (BDBA) recently has been changed to design extension conditions (DEC). DEC is required to be considered in the design process, and it comprises conditions in events without core melt and conditions in events with core melt. DEC with core melt is a part of severe accident. A systematic and deterministic approach to select DEC without core melt for a pressurized water reactor (PWR) is introduced.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2017

TORCHE - Toolbox for Reactor Cross-Flow Heat Exchangers

As interest within the scientific community for the development of small modular reactors (SMRs) grows, utilizing compact and cross-flow heat exchangers present many design advantages. Cross-flow configurations of tube bundles allow water, liquid metal, or a molten salt to be contained within the tube side or shell side in an efficient spatial arrangement. The goal of this project is to provide the user with an easy-to-use set of tools for cross-flow heat exchanger design. The tools are intended to require little to no geometric set-up like meshing in a CFD code in order to enable rapid preliminary design and optimization. With this set of simple Python scripts, the user can determine the necessary quantities and correctional factors in order to assess the heat exchanger characteristics. The two characteristics used in designing novel and efficient heat exchangers incorporated into this work currently are pressure drop and heat transfer coefficients. In support of these efforts, the literature has been scoured for sources of experimental data and proposed methods for calculating pressure drop and heat transfer in cross-flow tube banks. Several empirical correlations and methodologies for calculating pressure drop and heat transfer incorporated into the Toolbox for Reactor Cross-Flow Heat Exchangers (TORCHE). TORCHE is an expansion on the cross-flow pressure drop scripts reported by Haefner et al.. Presented in this summary is a synopsis of the empirical correlations and methodologies of pressure drops and heat transfer coefficient. A validation effort of these models is also presented to provide confidence in the implementation. For this validation of TORCHE, experimental data has been gathered and extracted from graphs in the literature. Error bars were not reported in the experimental data used in this summary and therefore is not included in the analysis.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2015

Understanding the consequences of hypothetical post-closure transient criticality in a geological disposal facility - 14439

Radioactive Waste Management (RWM) is responsible for implementing geological disposal of the UK's higher-activity radioactive wastes. These wastes include significant quantities of fissile nuclides and, therefore, demonstration of criticality safety for the wastes under disposal conditions forms an important component of RWM's disposal system safety case. At the time of disposal all waste packages will be safely sub-critical. Containment provided by the engineered barrier system of a geological disposal facility (GDF) will ensure that criticality is not possible for some time after disposal. However, as waste packages degrade, fissile and other materials may be mobilised, which could affect the potential for criticality. Although the likelihood of a critical configuration developing is demonstrably low, it cannot be assumed to be zero over long post-closure timescales. The UK environment agencies' Guidance on Requirements for Authorisation for a GDF includes a specific requirement to consider the consequences of hypothetical 'what-if' post-closure criticality. RWM has undertaken a programme of research to model and understand the consequences of hypothetical post-closure criticality events. Initially focused on the scenario of fissile material relocation and accumulation following intermediate level waste (ILW) disposal, two bespoke computer models were developed. The quasi-steady-state (QSS) model considered critical systems maintained by accumulation of fissile materials where the temperature feedback remains negative throughout the transient. The rapid transient model (RTM) considered systems with positive temperature feedback. The QSS model development included a successful comparison with the Oklo natural reactors. With a requirement to consider post-closure criticality for a wider range of potential waste types under different illustrative disposal concepts, the initial transient criticality models had some limitations. For the QSS model this was the assumption of fixed geometry, while the complex functional inputs required in the RTM were not readily available for different materials. For the QSS model this paper describes the model development to allow changing volume; this has enabled its application to 'what-if' scenarios of flooding within a spent fuel waste package and the slumping of a stack of ILW packages. For rapid transient criticality this paper explains how the development of a simpler 'bounding approach' model to complement the RTM has enabled transient criticality analysis for a wider range of host materials. The role of this research in demonstrating post-closure criticality safety of a GDF in the UK is presented in a companion paper which also draws on the results of a parallel research project to demonstrate that the likelihood of post-closure criticality is low. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗