Relevant bibliographies by topics / Reaction engineering (excl. nuclear reactions)

Academic literature on the topic 'Reaction engineering (excl. nuclear reactions)'

Author: Grafiati
Published: 10 December 2022
Last updated: 28 January 2023

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Journal articles on the topic "Reaction engineering (excl. nuclear reactions)"

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Shen, Yang-Ping, Bing Guo, and Wei-Ping Liu. "An indirect technique in nuclear astrophysics: alpha-cluster transfer reaction." EPJ Web of Conferences 260 (2022): 01001. http://dx.doi.org/10.1051/epjconf/202226001001.

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Helium(4He, or α)is the second most abundant element in the observable Universe. The α-particle induced reactions such as(α, γ), (α, n) and (α, p) play a crucial role in nuclear astrophysics, especially for understanding stellar heliumburning. Because of the strong Coulomb repulsion, it is greatly hindered to directly measure the cross sections for these α-capture reactions at stellar energies. Alpha-cluster transfer reaction is a powerful tool for investigation of astrophysical(α, γ), (α, n)and(α, p)reactions since it can preferentially populate the natural-parity states with an α-cluster structure which dominantly contribute to these astrophysical α-capture reactions during stellar heliumburning. In this paper, we reviewthe theoretical scheme, theexperimental technique, astrophysical applications and the future perspectives of such approach based on α-cluster transfer reactions.
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Liu, Z. Y., K. Li, Y. L. Yao, Z. Lei, C. T. Zhou, S. P. Zhu, X. T. He, and B. Qiao. "Enhancement of nuclear reactions via the kinetic Weibel instability in plasmas." Plasma Physics and Controlled Fusion 63, no. 12 (November 15, 2021): 125030. http://dx.doi.org/10.1088/1361-6587/ac2e41.

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Abstract Nuclear reactions in the plasma environment can be substantially different from those in conventional laboratory non-plasma cases, which have attracted considerable attention in the fields of fusion and astrophysics. To self-consistently model the nuclear reaction process during plasma dynamic evolution, an extended nuclear reaction calculation module is developed and included in two-dimensional particle-in-cell simulations. Through the self-consistent simulations, we systematically show that, apart from the plasma screening, the kinetic Weibel instability (WI) occurring in plasmas also results in significant enhancement of nuclear reactions, where the self-generated magnetic fields play a key role. Specifically, the self-generated magnetic fields in WI deflect ion motions, decreasing the relative velocity, and convert plasma kinetic energy to thermal energy, increasing the ion temperature. The simulation results show that, for the t ( d , n ) α reaction with a sharp resonance peak in the cross section, the reaction product yield is enhanced four times due to the WI. For nuclear reactions that have more prominent resonance peaks in the cross section, like 12 C ( p , γ ) 13 N , it is expected that such enhancements can reach up to one or several orders of magnitude.
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Perissi, Ilaria, and Ugo Bardi. "Revisiting the Mousetraps Experiment: Not Just about Nuclear Chain Reactions." Systems 10, no. 4 (June 29, 2022): 91. http://dx.doi.org/10.3390/systems10040091.

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We present here the first quantitative measurements of a classic experiment, that of the “mousetrap chain reaction”. It was proposed for the first time in 1947 to illustrate the chain reaction occurring in nuclear fission. It involves several spring-loaded mousetraps loaded with solid balls. Once one trap is made to snap, it releases two balls that may trigger the other traps. The result is a chain reaction that rapidly flares and then subsides as most traps have been triggered. The experiment has been popular as a scientific demonstration, but it does not seem that quantitative data were ever reported about it, nor that it was described using a model. We set out to do exactly that, and we can report for the first time that the mousetrap experiment can be fitted by a simple dynamic model derived from the well-known Lotka-Volterra one. We also discuss the significance of this experiment beyond nuclear chain reactions, providing insight into a variety of fields (chemistry, biology, memetic, natural resources exploitation) involving complex adaptive systems.
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Shaker Mehdy, Hala, Nariman Jabbar Qasim, Haider Hadi Abbas, Israa Al_Barazanchi, and Hassan Muwafaq Gheni. "Efficient time-series forecasting of nuclear reactions using swarm intelligence algorithms." International Journal of Electrical and Computer Engineering (IJECE) 12, no. 5 (October 1, 2022): 5093. http://dx.doi.org/10.11591/ijece.v12i5.pp5093-5103.

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In this research paper, we focused on the developing a secure and efficient time-series forecasting of nuclear reactions using swarm intelligence (SI) algorithm. Nuclear radioactive management and efficient time series for casting of nuclear reactions is a problem to be addressed if nuclear power is to deliver a major part of our energy consumption. This problem explains how SI processing techniques can be used to automate accurate nuclear reaction forecasting. The goal of the study was to use swarm analysis to understand patterns and reactions in the dataset while forecasting nuclear reactions using swarm intelligence. The results obtained by training the SI algorithm for longer periods of time for predicting the efficient time series events of nuclear reactions with 94.58 percent accuracy, which is higher than the deep convolution neural networks (DCNNs) 93% accuracy for all predictions, such as the number of active reactions, to see how the results can improve. Our earliest research focused on determining the best settings and preprocessing for working with a certain nuclear reaction, such as fusion and fusion task: forecasting the time series as the reactions took 0-500 ticks being trained on 300 epochs
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Vykhodets, V. B., T. E. Kurennykh, A. Yu Nikolaev, A. V. Suzdaltsev, and Yu P. Zaikov. "Determination of lithium content in solids by nuclear reaction technique." Diagnostics, Resource and Mechanics of materials and structures, no. 4 (August 2020): 28–34. http://dx.doi.org/10.17804/2410-9908.2020.4.028-034.

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The acceleration method of nuclear reactions is used to measure the content of lithium and oxygen in zirconium oxides. The purpose of the study stems from the fact that there are no direct methods for determining lithium concentration in solids, while lithium is currently widely used for alloying alloys in aircraft construction, nuclear power engineering, electrochemical devices, and other fields of technology. It is shown that satisfactory metrological characteristics of the method are provided when using the 6Li(d, p0)7Li and 7Li(d, p)8Li reactions at a deuteron energy of 650 keV.
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Strohmaier, Brigitte. "Reaction-model calculations of cross sections for neutron-induced reactions on 23Na." Annals of Nuclear Energy 20, no. 8 (August 1993): 533–45. http://dx.doi.org/10.1016/0306-4549(93)90002-7.

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Sultana, Irin, Alfredo Estradé, Jessica Borowiak, Jacob Elliott, Bradley S. Meyer, and Hendrik Schatz. "Sensitivity Study of Type-I X-ray Bursts to Nuclear Reaction Rates." EPJ Web of Conferences 260 (2022): 11040. http://dx.doi.org/10.1051/epjconf/202226011040.

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Type-I X-ray bursts are frequently occurring thermonuclear runaways on the surface of an accreting neutron star. The different nuclear reactions that empower the cataclysmic event play a key role in accurately comparing theoretical models and observations. We investigate the effect of the uncertainties in the nuclear reactions using a ONEZONE model for a set of different compositions and accretion rates that are within the range of the standard observed burst sources. A combination of a full-reaction network and a semi-analytic model is used to obtain the conditions at the time of X-ray burst ignition via simulating the settling process of the accreted material. We then evaluate the sensitivity of the X-ray burst model by varying the proton and alpha-induced reaction rates in JINA REACLIBV2.2 within representative nuclear physics uncertainties.
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Yamaguchi, H., S. Hayakawa, N. R. Ma, H. Shimizu, K. Okawa, L. Yang, D. Kahl, et al. "Experimental studies on astrophysical reactions at the low-energy RI beam separator CRIB." EPJ Web of Conferences 260 (2022): 03003. http://dx.doi.org/10.1051/epjconf/202226003003.

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Experimental studies on astrophysical reactions involving radioactive isotopes (RI) often accompany technical challenges. Studies on such nuclear reactions have been conducted at the low-energy RI beam separator CRIB, operated by Center for Nuclear Study, the University of Tokyo. We discuss two cases of astrophysical reaction studies at CRIB; one is for the 7Be+n reactions which may affect the primordial 7Li abundance in the Big-Bang nucleosynthesis, and the other is for the 22Mg(α, p) reaction relevantin X-raybursts.
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Holden, N. E. "Temperature Dependence of the Westcott g-factor for Neutron Reactions in Activation Analysis." Pure and Applied Chemistry 71, no. 12 (January 1, 1999): 2309–15. http://dx.doi.org/10.1351/pac199971122309.

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The Westcott g-factors, which allow the user to determine reaction rates for nuclear reactions taking place at various temperatures, have been calculated using data from the Evaluated Neutron Nuclear Data Library, ENDF/B-VI. Nuclides chosen have g-factors which are significantly different from unity and result in different reaction rates compared to nuclides whose neutron capture cross section varies as the reciprocal of the neutron velocity. Values are presented as a function of temperature up to 673.16 K (400 °C).
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Joseph Jeremiah, J., Damewan Suchiang, and B. M. Jyrwa. "Excitation functions of (n,2n) reactions for stable lead isotopes from reaction threshold to 20MeV." Annals of Nuclear Energy 56 (June 2013): 44–47. http://dx.doi.org/10.1016/j.anucene.2013.01.017.

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Conference papers on the topic "Reaction engineering (excl. nuclear reactions)"

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Doi, Daisuke. "Hydrogen Release Reaction From Sodium Hydride With Different Sample Quantities." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-91847.

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Abstract In sodium-cooled fast reactors (SFRs), hydrogen is a major nonmetallic impurity in the coolant during normal operation. A higher hydrogen concentration than the gas-liquid equilibrium had been transiently detected in the gas space of the actual SFR plant. However, the chemical reactions that caused hydrogen generation, which involve several sodium compounds, have not been identified. Furthermore, the thermal behavior of these hydrogen release reactions has not been thoroughly investigated. In this study, the hydrogen release behavior of sodium hydride, which could be involved in all of these reactions, was clarified by two experimental methods dealing with different sample quantities. In the thermal analysis with a semi-micro sample of about 1mmol, the hydrogen generation was demonstrated by mass spectrometry as the sample mass decreased, suggesting thermal decomposition. A monomodal hydrogen release curve similar to the thermal analysis result was obtained in the heating experiment with a macro amount sample of about 1mol. These experimental results showed consistent activation energies within the standard error. Therefore, it was elucidated that the ideal reaction behavior obtained by thermal analysis could be sufficiently extrapolated to the reaction behavior occurring in a larger amount of sample. These findings provide fundamental insights into the thermal decomposition of sodium hydride and are indispensable for analyzing hydrogen release behavior in other hydrogen release reactions involving sodium hydride.
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Kakavand, Tayeb, Morteza Taghilo, and Mahdi Sadeghi. "Determination of 89Zr Production Parameters via Different Reactions Using ALICE and TALYS Codes." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-30298.

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The 89Zr radioisotope is used in the field of tumor diagnostics, tumor therapy and the investigation of the biokinetic. The present work is investigated a suitable reaction to produce 89Zr..The Zirconium-89 excitation function via 89Y(p,n)89Zr, 89Y(d,2n)89Zr, natZr(p,pxn)89Zr, natSr(α,xn)89Zr and 90Zr(n,2n)89Zr reactions were calculated by ALICE-91 and TALYS-1.0 codes and the reaction of 89Y(p,n)89Zr has been selected. The calculated excitation function of 89Y(p,n)89Zr reaction was compared with the reported measurement and evaluations. Requisite thickness of targets was obtained by SRIM code for all above reactions except the 90Zr(n,2n)89Zr reaction. The 89Zr production yield was evaluated with attention to excitation function and stopping power for all above reactions except 90Zr(n,2n)89Zr reaction.
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Ghoranneviss, Mahmoud, Babak Malekynia, Nader Azizi, Henrich Hora, and George H. Miley. "Alternative Laser Driven Fusion Reactions for Nuclear Energy Without Radioactivity." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29945.

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Following the first result of generating nuclear fusion energy without dangerous radioactive radiation by laser ignition of the proton-11Boron reaction (HB11), we applied this method to evaluate other fusion reactions with no primary neutron production as the proton-7Lithium reaction (HLi7) and of the burning of solid density helium isotope 3He (He3-He3). The new method is a combination of now available laser pulses of 10 petawatt (PW) power and duration in the range of picoseconds (ps) or less. The new mechanism follows the initial theory of Chu and of Bobin for side-on ignition of solid state density fusion fuel developed in about 1972 where some later known physics phenomena had to be added. The essential innovation is the use of the discovery of a predicted anomaly when the mentioned laser pulses are sufficiently clean, i.e. free from prepulses by at least a contrast ratio 108 where acceleration by the nonlinear (ponderomotive) force is dominating.
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Kakavand, Tayeb, and Morteza Taghilo. "Calculations of Excitation Functions to Produce 88Y via Various Nuclear Reactions by ALICE/91 and TALYS-1.0 Codes." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-30328.

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Excitation functions were calculated by the ALICE/91 and TALYS-1.0 codes for natRb(a,xn)88Y, natZr(p,pxn)88Y, natSr(a,xn)88Y, 89Y(p,n)88Y and 88Sr(p,n)88Y reactions. The calculated cross sections were compared with the experimental data. The suitable energy ranges for the production of 88Y for each reaction is reported. From the excitation functions, integral yields of the products were calculated. Finally the suitable reaction was selected for the production of 88Y.
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Hamada, Hirotsugu, Akikazu Kurihara, and Masahiro Nishimura. "Study of Thermal Influence on Tubes Due to Sodium-Water Reactions in LMFBR Steam Generator." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49064.

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A study of thermal influence on heat-transfer tubes in sodium-water reactions is carried out to evaluate the tube rupture due to overheating in the water leak accident of an LMFBR steam generator (SG). By assuming the sodium-water reaction jet to be a two-phase flow that consists of sodium and hydrogen, the heat-transfer characteristics are examined and a simple model of effective heat-transfer coefficient (HTC) is proposed for the safety evaluation of the SG. Comparison of the model with experimental data leads to the following conclusions: An upper limit exists in the HTC between reaction jet and tube wall, and it is equivalent in approximation to the HTC of single-phase sodium flow. The HTC can be written in simple form as functions of the HTC of single-phase sodium flow, void fraction and temperatures of sodium, hydrogen and tube wall. Hydrogen provides negligible heating effect, so that the apparent HTC would decrease with increase of the hydrogen temperature that can readily surpass that of sodium. The outer-surface temperature of tube wall would not rise so high beyond the temperature of sodium that is excellent in heat-transfer characteristics, even if tube wall is exposed to the high-temperature hydrogen. The transient heat conduction analysis with the mean value of the data can appropriately evaluate the outer-surface temperature of tube wall by the metallographic observation, while the analysis with the maximum value can conservatively evaluate the tube wall temperature.
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Miley, G. H., C. Castano, A. Lipson, S. O. Kim, and N. Luo. "Progress in Development of a Low Energy Reaction Cell for Distributed Power Applications." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22148.

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Power units using Low Energy Nuclear Reactions (LENRs) potentially offer a radical new approach to power units that could provide distributed power units in the 1–50 kW range. As described in prior ICONE papers [9, 23] these cells employ thin metallic film cathodes (order of 500 Å, using variously Ni, Pd and Ti) with electrolytes such as 0.5–1 molar lithium sulfates in light water. Power densities exceeding 10 W/cc in the films have been achieved. An ultimate goal is to incorporate this thin-film technology into a “tightly packed” cell design where the film material occupies ∼ 20% of the total volume. If this is achieved, power densities of ∼20 W/cm3 appear feasible, opening the way to a number of potential applications involving distributed power. Recent studies reported here have concentrated on new electrode designs intended to maximize the proton loading in the films while maintaining the required proton and electron current densities.
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Wang, Xiaolin, Suraj C. Zunjarrao, Hui Zhang, and Raman P. Singh. "Advanced Process Model for Polymer Pyrolysis and Uranium Ceramic Material Processing." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89099.

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Silicon carbide (SiC) based uranium ceramic material can be fabricated as hosts for ultra high temperature applications, such as gas-cooled fast reactor fuels and in-core materials. A pyrolysis-based material processing technique allows for the fabrication of SiC based uranium ceramic materials at a lower temperature compared to sintering route. Modeling of the process is considered important for optimizing the fabrication and producing material with high uniformity. This study presents a process model describing polymer pyrolysis and uranium ceramic material processing, including heat transfer, polymer pyrolysis, SiC crystallization, chemical reactions, and species transport of a porous uranium oxide mixed polymer. Three key reactions for polymer pyrolysis and one key reaction for uranium oxide polymer interaction are established for the processing. Included in the model formulation are the effects of transport processes such as heat-up, polymer decomposition, and volatiles escape. The model is capable of accurately predicting the polymer pyrolysis and chemical reactions of the source material. Processing of a sample with certain geometry is simulated. The effects of heating rate, particle size and volume ratio of uranium oxide and polymer on porosity evolution, species uniformity, reaction rate are investigated.
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Yiren, Lian, Sun Hongchao, Chen Lei, Meng Dongyuan, Li Guoqiang, Zhuang Dajie, Sun Shutang, and Zhang Jiangang. "Review and Security Assessment of Red Oil Explosions in Evaporator." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-82221.

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Purex progress is widely applied in the nuclear fuel reprocessing plants all over the world. However, various security problems occur in reprocessing facility involving the intense attention of red oil explosion. The exothermic reactions among TBP, nitric salts and nitric acid were responsible for the red oil explosion. In this paper, explosion events at nuclear fuel reprocessing plants initiated by red oil phenomena were reviewed. The formation and reaction mechanisms of red oil causing explosions were analyzed. Moreover, the evaluation and analysis model was built up to evaluate the security assessment of red oil explosion from the associated calculations of data in the typical red oil explosive accidents and the results of subsequent laboratory studies on the chemical reaction.
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Yang, Yi, Yiguo Li, and Bin Zhao. "Physics Design of Special Epithermal Neutron Beam Based on Multi D-D Reaction Neutron Tubes." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81392.

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Accelerator used for Boron Neutron Capture Therapy (BNCT) is the development trend of cancer treatment in the future. Neutron generator is a neutron source with compact structure, easy to operate, and lower price in accelerator (the structure of neutron tube is more compact). It has a high feasibility of establishing in the hospital when compared with other types of accelerator. At present, the D-D reaction has higher neutron yield than other reactions, more easy to get D material. Therefore, the epithermal neutron beam based on D-D neutron generator is studied for BNCT usage. First, the calculation model is established by MCNP program, including the neutron source model, the geometric model of the irradiation device. The specific neutron energy spectrum and angular distribution of the D-D reaction are theoretically analyzed when establishing the D-D reaction neutron source model. The basic structure models of typical irradiation devices are designed, and then the optimal suitable moderator material for the irradiation device is studied from the neutron reaction cross section, the combination of iron and Fluental materials is optimum. The irradiation device with multi D-D neutron tubes’ combination as BNCT neutron source is designed. It can be concluded by study that the parameters at the beam exit are epithermal neutron flux density 2.01 × 108 n/cm2 · s, fast neutron contamination 1.33 × 10−11 Gy · cm2/n, γ contamination 5.79 × 10−17 Gy · cm2/n, for the combination with 6 neutron tubes. The result can meet IAEA’s requirements for BNCT epithermal neutron beam quality.
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Himi, Masashi, Hiroshi Kozakai, Yuichi Yamamoto, Seigo Hosoda, Noriyuki Shirakawa, and Tatsumi Arima. "R&D of the Next Generation Safety Analysis Methods for Fast Reactors With New Computational Science and Technology: 6 — Study of Eutectic Reaction Between Metals: FPMD Approach." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48482.

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A five-year research project started in FY2005 to develop a code based on the MPS (Moving Particle Semi-implicit) method for detailed analysis of core disruptive accidents (CDAs) in sodium-cooled fast reactors (SFRs). The code is named COMPASS (Computer Code with MPS for Reactor Safety Analysis) [1]. In this project, both mixed-oxide (MOX) and metal fuels are considered as a fuel material component. One of the main features of the project is to investigate eutectic reactions between the metal fuel and the cladding/structure materials with phase diagram calculation, classical and first principle molecular dynamics (CMD and FPMD) methods. This paper presents outcomes from study with FPMD.
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