A5038223082- Nuclear reactor physics and engineering
- Fusion materials and technologies
- Nuclear Physics and Applications
- Graphite, nuclear technology, radiation studies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Nuclear and radioactivity studies
- Superconducting Materials and Applications
- Advanced Radiotherapy Techniques
- Radiation Detection and Scintillator Technologies
- Radiation Dose and Imaging
- Ion-surface interactions and analysis
- Manufacturing Process and Optimization
Karlsruhe Institute of Technology
2021-2023
Oak Ridge National Laboratory
2023
University of Wisconsin–Madison
2016-2022
Fusion Academy
2017
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....
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 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...
Modeling and simulation lie at the heart of design process any nuclear application. An accurate representation radiation environment ensures not only feasibility new technologies, but it also aids in operation, maintenance, even decommissioning. With increasingly complex designs, high-fidelity models have become a necessity for maturity. McCAD has been under development many years Karlsruhe Institute Technology (KIT) to facilitate generating suitable analyses. In this paper, an overview...
The Fusion Nuclear Science Facility (FNSF) is viewed as an essential element of the US developmental roadmap to fusion energy. spherical tokamak-based FNSF has been designed through a national collaborative effort led by Princeton Plasma Physics laboratory. High-temperature superconducting (HTS) magnets are potentially attractive for such applications. Among other aspects, magnet shielding and tritium breeding assessments represent key elements achieving design engineering objectives....
Two issues related to neutronics analysis of fusion systems were addressed for the purpose physical design iterations as well plant operation: tritium self-sufficiency and shielding inboard magnet. State-of-the-art modeling/analysis tools facilitated a full 3-D latest FESS-FNSF design. The first stage involved selection materials wall blanket along with protect magnet based on extensive 1-D analyses. second is stepwise workflow estimate overall breeding ratio high fidelity. It bottom-up...
In this work, a preliminary assessment of the shutdown dose rate (SDR) in latest Fusion Energy Systems Studies–Fusion Nuclear Science Facility conceptual design was calculated for one sector at different maintenance stages. The third operational phase, deuterium-tritium 2.75 years, considered to define neutron source and Rigorous 2-Step workflow used. SDR levels were obtained times that correspond major operations found be above 105 µSv/h, which necessitates robotic handling all operations.
In fusion energy systems, part of the design effort is dedicated to assessment shutdown dose rate (SDR) due decay photons that will be emitted from activated components. Monte Carlo transport codes are often used obtain neutron flux distribution in problem domain. The rigorous 2-step (R2S) workflow photon emission density decaying radionuclides. then as an input for a step calculate SDR. this paper, uncertainty gamma source R2S investigated. A scheme developed estimate source, building on...
ITER is an international collaborative effort towards the realization of fusion energy via magnetic confinement concept. Two equatorial ports in facility are dedicated to testing tritium breeding concepts, which essential for self-sufficiency future reactors. The concerned Test Blanket System (TBS) consists a Module (TBM) residing inside TBM–Port Plug (TBM-PP) and its associated ancillary systems Tokamak facility. In this paper, results full suite nuclear analyses concerning shielding...