Article
Physics, Fluids & Plasmas
Byung Chul Kim
Summary: The nuclear fusion waste generated by the Korean fusion DEMOnstration reactor (K-DEMO) is evaluated and classified according to Korean regulations. The majority of the waste is categorized as intermediate-level waste (ILW) and measures will be taken to minimize ILW fraction in waste disposal strategies.
Article
Nuclear Science & Technology
N. Asakura, K. Hoshino, S. Kakudate, F. Subba, J. -h. You, S. Wiesen, T. D. Rognlien, R. Ding, S. Kwon
Summary: The power exhaust concept and divertor design are critical issues in tokamak DEMO design activities worldwide. Radiative cooling is commonly used for power fusion scenarios. Challenges include increasing main plasma radiation fraction for ITER-level P-sep/R-p designs, extending ITER divertor geometry, and optimizing the divertor design for large P-sep. Power exhaust simulations with large P-sep have been performed, showing extended plasma detachment and reduced heat load with the right divertor radiation fraction.
NUCLEAR MATERIALS AND ENERGY
(2023)
Article
Physics, Fluids & Plasmas
N. Asakura, K. Hoshino, S. Kakudate, F. Subba, C. Vorpahl, Y. Homma, H. Utoh, Y. Someya, Y. Sakamoto, R. Hiwatari, S. Suzuki, J-H You, M. Siccinio, G. Federici
Summary: Concepts for power exhaust and divertor design have been developed with high priority in the pre-conceptual design phase of the Japan-Europe broader approach DEMO design activity. Different exhaust concepts for main plasma and divertor have been proposed by Japan and Europe to address the large power exhaust and radiative cooling issues. Power exhaust simulations showed the need for a large divertor radiation fraction to reduce peak heat flux and electron and ion temperatures.
Article
Physics, Multidisciplinary
R. Rayaprolu, S. Moeller, I Spahn, D. Hoschen, Ch Linsmeier
Summary: In a pilot experiment, 16 MeV protons were used to irradiate 300 μm thick W samples to a damage dose of 0.006 dpa under low and high temperature conditions. The electronic loss in the sample was observed to be 1.5 MW·m(-2) in the pre-Bragg region. Post high-temperature irradiation, recrystallization of the W sample was observed, leading to a surface softening of 0.6 GPa.
Article
Chemistry, Analytical
Sun Il Kim, Ki Tae Yang, Jong Soon Song
Summary: The study examined the establishment of an integrated waste tracking system in Korea based on an analysis of domestic and overseas systems to consolidate the classification criteria of different entities. Codes were assigned to locations where waste is processed and stored to offer scenarios based on movements between these locations.
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
(2021)
Article
Nuclear Science & Technology
Giuseppe A. Marzo, Luigi Lepore, Riccardo Levizzari, Luigi Di Pace, Nadia Cherubini
Summary: Future nuclear fusion reactors will generate radioactive waste, including activation products and Tritium, requiring appropriate measurement techniques for monitoring. The use of solid state detectors can reduce measurement time and provide a basis for quantifying radionuclides.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Energy & Fuels
Seungbin Yoon, Woo Nyun Choi, Jaehoon Byun, Hee Reyoung Kim
Summary: The feasibility of synthesizing graphene quantum dots from spent resin in a decommissioned nuclear power plant was experimentally analyzed, and the resulting reduction in disposal cost was estimated. Graphene quantum dots were successfully synthesized using uncontaminated ion-exchange resin, and various analytical techniques confirmed the possibility of recycling the spent resin. The estimated reduction in disposal cost indicates a significant decrease, showcasing the potential financial benefits of this recycling method.
INTERNATIONAL JOURNAL OF ENERGY RESEARCH
(2022)
Article
Energy & Fuels
Bong-Guen Hong
Summary: The optimal shape of a fusion-based transmutation reactor with a molten salt coolant was determined by analyzing plasma physics, technology, and neutronic requirements. It was found that a reactor with a large aspect ratio had smaller size, higher maximum fusion power, and enhanced tritium-breeding capability.
Article
Materials Science, Multidisciplinary
N. N. Duy, T. M. Tien, N. N. Le, Thu D. H. Truong
Summary: This study examined the reaction cross sections for the destruction of Tc-99 nuclide, a long-lived exotic element found in nuclear fuel and radioactive waste. Different theoretical models were used to calculate the cross sections, and a large uncertainty was found due to the variation in these models. The (p, n), (alpha, n), and (n, gamma) reactions were suggested for the transmutation of Tc-99. The reliability of the models was assessed by comparing the calculated cross sections with evaluated data in the ENDF database, and the Constant-temperature Fermi Gas and Kopecky-Uhl Generalized Lorentzian models were found to be the most reliable. Overall, this study is important for improving the transmutation of radioactive waste and understanding the factors affecting cross section.
RESULTS IN PHYSICS
(2022)
Article
Construction & Building Technology
I. Yu Zel, M. Kenessarin, S. E. Kichanov, M. Balasoiu, D. P. Kozlenko, K. Nazarov, M. Nicu, L. Ionascu, A. C. Dragolici, F. Dragolici
Summary: Neutron tomography was used to study the spatial arrangement of graphite in cement-based materials, revealing the distributions of average sizes, orientation, and shape-related parameters of the graphite particles. The elastic properties of graphite-containing cement materials were calculated based on the obtained structural features of the morphology of graphite phase.
CEMENT & CONCRETE COMPOSITES
(2021)
Article
Multidisciplinary Sciences
Lin Song, Huixuan Zhao, Zongfang Ma, Qi Song
Summary: This study proposes a two-level fusion-based method for the classification of construction waste. The method utilizes statistical histograms and gradient histograms, encodes and fuses visual features using the bag-of-visual-words method, and achieves automatic classification of construction waste through a joint decision-making model.
Article
Metallurgy & Metallurgical Engineering
M. H. Sadeghi, M. Outokesh, M. Sharifi, M. Habibi Zare
Summary: The study aimed to develop a process for recovering uranium from carbonaceous radioactive waste through leaching with Al(NO3)3 and nitric acid, extraction with TBP/kerosene, and stripping with dilute nitric acid, resulting in a purified uranyl nitrate solution suitable for reuse in UF6 production plants.
Article
Nuclear Science & Technology
Simona Breidokaite, Gediminas Stankunas
Summary: WCLL and HCPB are two leading breeding blanket concept candidates for the EU-DEMO reactor. WCLL uses Lithium-Lead alloy as a breeding material, HCPB uses lithium orthosilicate, and both have cooling tubes. The estimation of neutron fluxes, nuclear heating and dose rates are crucial for assessing the nuclear performance of the breeding blankets. This paper used MCNP6 with FENDL-3.2 nuclear data library and ADVANTG to perform necessary calculations.
JOURNAL OF FUSION ENERGY
(2023)
Article
Physics, Fluids & Plasmas
S. S. Ananyev, B. V. Ivanov, A. Yu. Dnestrovskij, A. S. Kukushkin, A. V. Spitsyn, B. V. Kuteev
Summary: This paper discusses the design of the DEMO-FNS fusion neutron source and explores new technological solutions for the tokamak fuel cycle, while analyzing the technology readiness level and integration potential in the Russian Federation.
Article
Nuclear Science & Technology
Shinya Yamasaki, Satoshi Utsunomiya
Summary: The Fukushima Daiichi Nuclear Power Plant accident in 2011 led to extensive radioactive contamination of soil, with plans in place for storing and disposing of the contaminated soil by 2045. The decommissioning of the plant will generate a significant amount of radioactive waste, making it crucial to address the reduction of contaminated soil volume. Technologies focusing on removing radioactive Cs, particularly Cs-137, from the soil are essential for effective management of the contaminated sites.
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY
(2022)
Article
Nuclear Science & Technology
Arkady Serikov, Luciano Bertalot, Maarten De Bock, Ulrich Fischer
Summary: The neutronic analysis presented in this paper supports the design development of the CXRS-Edge system for installation in the Equatorial Port #3 of ITER. The analysis evaluates the shielding performance and radiation effects, as well as nuclear reactions in materials like molybdenum, steel, and silicon carbide. Additionally, the feasibility of accessing the Inter-Space Structure of EP3 with the CXRS-Edge system installed was assessed through shutdown dose rate mapping.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Nuclear Science & Technology
D. Leichtle, U. Fischer, C. Bachmann
Summary: The European fusion programme aims to design a demonstration fusion power plant (DEMO) with a strong focus on the role of neutronics in the design, operation, and safety of nuclear facilities. Conducted by the EUROfusion consortium, the work includes supporting research and development programs, as well as the design of a high-intensity neutron source for qualification of materials. To strengthen nuclear design integration, a coordinated approach for neutronics is essential, relying on computational procedures, tools, and data, and aligning with global nuclear design integration principles.
FUSION SCIENCE AND TECHNOLOGY
(2021)
Article
Instruments & Instrumentation
Prasoon Raj, Maurizio Angelone, Ulrich Fischer, Axel Klix
Summary: The study examined the applicability of self-powered detectors (SPDs) for radiation monitoring in fusion reactor blankets. A specially designed Cr-SPD was tested under intense gamma-ray and neutron sources, with Monte Carlo modeling used for detailed signal analysis. The results showed good performance of the model, providing valuable insights for improving traditional SPD simulation techniques.
REVIEW OF SCIENTIFIC INSTRUMENTS
(2021)
Article
Physics, Fluids & Plasmas
Luca Reali, Max Boleininger, Mark R. Gilbert, Sergei L. Dudarev
Summary: In this study, we propose a method for computing macroscopic elastic stress and strain in components of a fusion power plant using the eigenstrain produced by defects in a material exposed to high energy neutron irradiation. Analytical and numerical analysis of several case studies related to the design of a fusion power plant show that the spatial distribution of defects leads to significant elastic stresses in ion-irradiated thin films, pressurized cylindrical tubes, and breeding blanket modules.
Article
Physics, Fluids & Plasmas
Sehila M. Gonzalez de Vicente, Nicholas A. Smith, Laila El-Guebaly, Sergio Ciattaglia, Luigi Di Pace, Mark Gilbert, Robert Mandoki, Sandrine Rosanvallon, Youji Someya, Kenji Tobita, David Torcy
Summary: In the absence of official standards and guidelines, fusion designers have adopted well-established standards for fission-based nuclear power plants. However, this approach may result in overconservative measures and increased cost and complexity. One important issue in fusion power is the generation of radioactive waste, which is significantly different from fission NPP waste. Fusion waste mainly consists of low-level and intermediate level waste, but without many long-lived isotopes. The use of reduced-activation materials in fusion technology allows for lower decay heat removal and rapid radioactivity decay.
Review
Energy & Fuels
Arunodaya Bhattacharya, Steven J. Zinkle, Jean Henry, Samara M. Levine, Philip D. Edmondson, Mark R. Gilbert, Hiroyasu Tanigawa, Charles E. Kessel
Summary: RAFM and ODS steels are the most promising candidates for fusion first-wall/blanket structures, but their performance will deteriorate due to neutron damage and gas effects during operation. Future development should target materials with lower chromium concentration to minimize irradiation-induced effects.
JOURNAL OF PHYSICS-ENERGY
(2022)
Article
Materials Science, Multidisciplinary
Shu Huang, Ryan Kerr, Samuel Murphy, Mark R. Gilbert, Jaime Marian
Summary: A numerical model is presented to predict oxide scale growth on tungsten surfaces under exposure to oxygen at high temperatures, with simulations showing deviations from classical parabolic growth in certain cases. The model is parameterized using experimental measurements and electronic structure calculations, with a comparison to extensive experimental data showing reasonable agreement at most temperatures. This work attempts to embed the thermodynamic and kinetic complexity of tungsten oxide growth into a comprehensive mesoscale kinetic model to fill existing knowledge gaps and guide future tungsten oxidation models.
MODELLING AND SIMULATION IN MATERIALS SCIENCE AND ENGINEERING
(2022)
Article
Nuclear Science & Technology
Sophia O. von Tiedemann, David M. Collins, Mark R. Gilbert, Ivan A. Kodeli
Summary: Predictions of material activity in commercial fusion conditions mostly rely on computational methods due to lack of data on long-term effects of high-energy neutron irradiation on structural steels. This study focused on modelling neutron activation of four structural steels in a fusion reactor environment after 20 years of operation. Eurofer and F82H steels exhibited higher resistance to neutron activation than G91 and SS316L(N)-IG. The vacuum vessel (SS316L(N)-IG) would not be classified as low-level waste for several centuries.
FUSION ENGINEERING AND DESIGN
(2023)
Article
Energy & Fuels
Mark R. Gilbert
Summary: Nuclear data is crucial for fusion experiments and future fusion power plants, as it provides information on neutron reaction probabilities and decay behavior. Inventory codes that use this data to predict the effects on materials are also important for managing radiological hazards and determining component lifetimes. Validated and accurate nuclear data and inventory codes are essential for the safe and efficient operation of fusion reactors.
JOURNAL OF PHYSICS-ENERGY
(2023)
Article
Materials Science, Multidisciplinary
Yichen Qian, Mark R. Gilbert, Lucile Dezerald, Duc Nguyen-Manh, David Cereceda
JOURNAL OF NUCLEAR MATERIALS
(2023)