A5022992571- Nuclear reactor physics and engineering
- Magnetic confinement fusion research
- Fusion materials and technologies
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Superconducting Materials and Applications
- Graphite, nuclear technology, radiation studies
- Radiation Therapy and Dosimetry
- Particle accelerators and beam dynamics
- Nuclear and radioactivity studies
- Laser-Plasma Interactions and Diagnostics
- Cryptography and Data Security
- Advanced Radiotherapy Techniques
- Manufacturing Process and Optimization
- Image Processing and 3D Reconstruction
- Adversarial Robustness in Machine Learning
- Space Satellite Systems and Control
- Adsorption and Cooling Systems
- RFID technology advancements
- Teaching and Learning Programming
- Smart Grid Security and Resilience
- Radiation Detection and Scintillator Technologies
- Catalysis and Oxidation Reactions
- Greenhouse Technology and Climate Control
- Computational Fluid Dynamics and Aerodynamics
Texas Instruments (United States)
2024
United Kingdom Atomic Energy Authority
2018-2024
Culham Centre for Fusion Energy
2009-2023
Culham Science Centre
2009-2023
University of Wisconsin–Madison
2013-2022
University of Wisconsin–Milwaukee
2018
Fusion Academy
2017
University of Michigan–Flint
2017
University of Wisconsin System
2015
University of Tennessee at Knoxville
2010
Abstract A fusion nuclear science facility (FNSF) could play an important role in the development of energy by providing environment needed to develop materials and components. The spherical torus/tokamak (ST) is a leading candidate for FNSF due its potentially high neutron wall loading modular configuration. key consideration choice configuration range achievable missions as function device size. Possible include: fluence, demonstrating tritium self-sufficiency, electrical self-sufficiency....
The proposed Fusion Nuclear Science Facility (FNSF) represents the first facility to enter complex fusion nuclear regime, and its technical mission attributes are being developed. FNSF one part of energy development pathway commercial power plant with other major components pre-FNSF research development, in parallel FNSF, pre-DEMO demonstration (DEMO). Energy Systems Studies group is developing basis for order provide a better understanding demands on plasma science programs.
Liquid metal (LM) plasma-facing components (PFCs) may provide a resolution to the challenging fusion environment, particularly first wall and divertor surfaces. Transforming these concepts into viable technologies will require considerable research development. With nuclear regime in mind, Fusion Energy System Studies group examined LM PFCs order identify needed thrusts that could accelerate their development assess viability. behavior, solid substrate aspects, facility integration aspects...
Neutronics analysis was performed on the latest Fusion Energy System Studies-Fusion Nuclear Science Facility (FESS-FNSF) design, which determined neutron wall loading, tritium breeding ratio, and radiation damage. Sixteen different sectors configurations were investigated, with main focus determining impact each has upon ratio (TBR) of whole facility. This paper describes stages nuclear that serve to prove derived attributes system.
The ARIES team has examined a multitude of fusion concepts over period 25 years. In recent years, the wrapped up Advanced Research, Innovation, and Evaluation Study (ARIES) series by completing detailed design ARIES–Advanced Conservative Tokamak (ARIES-ACT2) power plant—a plant with conservative physics technology, representing tokamak reduced-activation ferritic/martensitic (RAFM) structure dual-coolant lead-lithium blanket. integration nuclear assessments (neutronics, shielding,...
The Spherical Tokamak for Energy Production (STEP) programme is an ambitious but challenging endeavour to design and deliver a prototype fusion power plant. It rapid, fast-moving programme, designing first of kind device in Volatile, Uncertain, Complex Ambiguous (VUCA) environment, digital tools play pivotal role managing navigating this space. Digital helps manage the complexity sheer volume information. Advanced modelling simulation techniques provide platform designers explore various...
Abstract To support the design of fusion reactors for energy production, there is an urgent need to develop multi-physics software tools capable modelling critical tokamak components as a single cohesive whole. Although some loosely-coupled physics do exist, these lack fidelity and will fundamentally fail capture any closed-loop feedback effects between separate modules. address this need, we introduce new open-source code: AURORA: A Unified Resource OpenMC (fusion) Reactor Applications....
Views Icon Article contents Figures & tables Video Audio Supplementary Data Peer Review Share Twitter Facebook Reddit LinkedIn Tools Reprints and Permissions Cite Search Site Citation P. U. Lamalle, B. Beaumont, T. Gassmann, F. Kazarian, Arambhadiya, D. Bora, J. Jacquinot, R. Mitteau, C. Schüller, A. Tanga, Baruah, Bhardwaj, Kumar, Mukherjee, N. Singh, Goulding, Rasmussen, Swain, G. Agarici, Sartori, A Borthwick, Davis, Fanthome, Hamlyn‐Harris, Hancock, Kaye, Lockley, M. Nightingale,...
The use of a liquid-metal (LM) plasma-facing component (LM-PFC) in fusion reactor designs has some advantages as well disadvantages compared to traditional that solid wall. Neutronics analysis these potential LM-PFC concepts is important order ensure radiation limits are met and system performance meets expectations.A three-dimensional (3-D) neutronics parametric study considering four LM first-wall (FW) candidates, (PbLi, Li, Sn, SnLi) was performed with thin (2.51-cm) design. 3-D used...
As part of the expansion Direct Accelerated Geometry Monte Carlo (DAGMC) toolkit to support other codes, FluDAG (FLUKA integrated with DAGMC) was developed. There has been increasing demand from high energy physics community regarding Computer Aided Design (CAD) geometry in codes. In this paper, development and validation is discussed its application a number experiments demonstrated, along validity relative native FLUKA calculations.
Breeding blankets are designed to ensure tritium self-sufficiency in deuterium–tritium fusion power plants. In addition this, breeder play a vital role shielding key components of the reactor, and provide main source heat which will ultimately be used generate electricity. Blanket design is critical success reactors integral process. Neutronic simulations regularly performed ascertain performance particular design. An iterative process improvements parametric studies required optimize meet...
During the conceptual design process of fusion reactors it is useful to rapidly prototype different concepts and assess their suitability against a range high level requirements. Rapid prototyping allows 'fail early' mantra other fields be applied engineering design. Furthermore, rapid generation low fidelity analysis fast exploration space, which enables better decisions made during concept selection detailed phase. The Paramak an open-source tool that aims provide automated parameter...
In this paper, we propose a version of RSA encryption that uses the Chinese Remainder Theorem (CRT) for purpose concealing multiple plain-texts in one cipher-text. This scheme allows sender to possibly send different information receivers, and each receiver is only able decrypt message intended them. We prove algorithm mathematically. Furthermore, our secure against chosen plain-text (CPA) attack. also compare textbook show security size advantages. The new can take advantage current methods...