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Journal articles on the topic 'Fusion-fission reactor system'

Author: Grafiati

Published: 4 June 2025

Last updated: 1 August 2025

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1

Murgo, Stefano, Guglielmo Lomonaco, Francesco Paolo Orsitto, Fabio Panza, and Nicola Pompeo. "Parametrical Choice of the Optimized Fusion System for a FFHR." Energies 17, no. 20 (2024): 5121. http://dx.doi.org/10.3390/en17205121.

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Fusion–fission hybrid reactors are concepts of subcritical reactors based on the coupling of fusion and fission devices. In this case, the fusion reactor would work as an external neutron supplier for the fission core of the machine. Such systems could, in principle, operate as multi-purpose machines, such as energy generators, breeders and waste burners. The large availability of fusion and fission technologies makes the choice of devices to couple quite chaotic. In fact, most of the concepts proposed in the literature are based on attempts without real optimization. The purpose of this paper

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2

Murata, I., S. Shido, M. Matsunaka, K. Kondo, and H. Miyamaru. "New burnup calculation system for fusion–fission hybrid reactor." Fusion Engineering and Design 82, no. 15-24 (2007): 2772–78. http://dx.doi.org/10.1016/j.fusengdes.2007.05.061.

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3

Murgo, Stefano, Chiara Bustreo, Marco Ciotti, et al. "RFP-MSR Hybrid Reactor Model for Tritium Breeding and Actinides Transmutation †." Energies 17, no. 12 (2024): 2934. http://dx.doi.org/10.3390/en17122934.

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The studies on the development of fusion–fission hybrid reactors (FFHR) have gained consensus in recent years as an intermediate step before fusion energy. This work proposes a possible approach to FFHRs based on the coupling of a Reversed Field Pinch fusion machine and a Molten Salt Subcritical fission test bed. The proposed test bed is characterized by the coexistence of a fast-neutron fission core and a dedicated thermal-neutron zone, allowing the performing of tritium breeding and actinides transmutation studies. The neutronic design solutions and the results obtained by the irradiation of

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4

Koshlan, Vladislav I., and Sergey S. Ananyev. "Analytical Simulation of the Fuel Cycle of Fusion and Hybrid Reactors." Vestnik MEI, no. 1 (2022): 19–38. http://dx.doi.org/10.24160/1993-6982-2022-1-19-38.

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The characteristic fuel cycle (FC) schemes for fusion and hybrid (fusion-fission) reactors are considered. The FC structures of the facilities that are under construction and of newly designed ones are analyzed. The FC architecture general features and specific ones of each facility are highlighted. Two simplified FC schemes are proposed, and a computer program for solving a system of differential equations and simulating the accumulation of fusion fuel component (tritium) in FC systems in a steady-state operation mode of the facilities has been developed. The obtained results are compared wit

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5

Koshlan′, Vladislav I., and Sergey S. Ananyev. "Analytical Simulation of the Fuel Cycle of Fusion and Hybrid Reactors." Vestnik MEI, no. 1 (2022): 19–38. http://dx.doi.org/10.24160//1993-6982-2022-1-19-38.

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The characteristic fuel cycle (FC) schemes for fusion and hybrid (fusion-fission) reactors are considered. The FC structures of the facilities that are under construction and of newly designed ones are analyzed. The FC architecture general features and specific ones of each facility are highlighted. Two simplified FC schemes are proposed, and a computer program for solving a system of differential equations and simulating the accumulation of fusion fuel component (tritium) in FC systems in a steady-state operation mode of the facilities has been developed. The obtained results are compared wit

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6

Shamanin, Igor V., Sergey V. Bedenko, Vladimir M. Shmakov, Dmitry G. Modestov, and Igor O. Lutsik. "Power density dynamics in a nuclear reactor with an extended in-core pulse-periodic neutron source based on a magnetic trap." Nuclear Energy and Technology 6, no. (3) (2020): 175–79. https://doi.org/10.3897/nucet.6.57976.

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The article examines the features of the spatial kinetics of an innovative hybrid nuclear power facility with an extended neutron source based on a magnetic trap. The fusion-fission facility under study includes a reactor plant, the core of which consists of an assembly of thorium-plutonium fuel blocks of the HGTRU reactor of a unified design and a long magnetic trap that penetrates the near-axial region of the core. The engineering solution for the neutron plasma generator is based on an operating gas-dynamic trap based on a fusion neutron source (GDT-FNS) developed at the Novosibirsk G.I. Bu

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7

Acır, Adem, and Taner Altunok. "Utilization of TRISO Fuel with LWR Spent Fuel in Fusion-Fission Hybrid Reactor System." Journal of Fusion Energy 29, no. 5 (2010): 436–42. http://dx.doi.org/10.1007/s10894-010-9301-3.

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8

Yu, Zhang-cheng, and Heng Xie. "Feasibility study of applying the passive safety system concept to fusion–fission hybrid reactor." Fusion Engineering and Design 89, no. 4 (2014): 370–77. http://dx.doi.org/10.1016/j.fusengdes.2014.03.049.

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9

Dai, Tao, Liangzhi Cao, Qingming He, Hongchun Wu, and Wei Shen. "A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR." Energies 13, no. 16 (2020): 4070. http://dx.doi.org/10.3390/en13164070.

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The China Fusion Engineering Test Reactor (CFETR) is a tokamak device to validate and demonstrate fusion engineering technology. In CFETR, the breeding blanket is a vital important component that is closely related to the performance and safety of the fusion reactor. Neutronics/thermal-hydraulics (N/TH) coupling effect is significant in the numerical analysis of the fission reactor. However, in the numerical analysis of the fusion reactor, the existing coupling code system mostly adopts the one-way coupling method. The ignorance of the two-way N/TH coupling effect would lead to inaccurate resu

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10

Shamanin, Igor V., Sergey V. Bedenko, Vladimir M. Shmakov, Dmitry G. Modestov, and Igor O. Lutsik. "Power density dynamics in a nuclear reactor with an extended in-core pulse-periodic neutron source based on a magnetic trap." Nuclear Energy and Technology 6, no. 3 (2020): 175–79. http://dx.doi.org/10.3897/nucet.6.57976.

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The article examines the features of the spatial kinetics of an innovative hybrid nuclear power facility with an extended neutron source based on a magnetic trap. The fusion-fission facility under study includes a reactor plant, the core of which consists of an assembly of thorium-plutonium fuel blocks of the HGTRU reactor of a unified design and a long magnetic trap that penetrates the near-axial region of the core. The engineering solution for the neutron plasma generator is based on an operating gas-dynamic trap based on a fusion neutron source (GDT-FNS) developed at the Novosibirsk G.I. Bu

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11

Andrianova, E. A., E. V. Rodionova, S. A. Subbotin, T. D. Schepetina, A. V. Gurin, and N. A. Kovalenko. "Effect of a Hybrid Fusion Plant Operating in a Fission and Fusion Reactor System on the Fuel Cycle." Physics of Atomic Nuclei 85, no. 8 (2022): 1342–49. http://dx.doi.org/10.1134/s1063778822080038.

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12

Zhang, Bin, Peng-Cheng Gao, Tao XU, Rong-Rong Qian, Mao-Lin Jing, and Jian-Qiang Shan. "Severe accident analysis of the dual-functional lithium-lead test blanket module using ISAA-DFLL code." Thermal Science 26, no. 5 Part B (2022): 4079–93. http://dx.doi.org/10.2298/tsci2205079z.

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The international thermonuclear experimental reactor (ITER) project aims to build a tokamak fusion test reactor to verify the feasibility of fusion reactors. The test blanket module (TBM) is the key component of the international thermonuclear experimental reactor. The fusion design study team proposed the concept of the dual-functional lithium-lead test blanket module (DFLL-TBM). The integral severe accident analysis (ISAA) is a self-developed ISAA code that models the progression of severe accidents in nuclear power plants. A broad spectrum of severe accident phenomena including fission prod

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13

Şahi̇n, Sümer, Hacı Mehmet Şahin, and Güven Tunç. "Monte Carlo analysis of LWR spent fuel transmutation in a fusion-fission hybrid reactor system." Nuclear Engineering and Technology 50, no. 8 (2018): 1339–48. http://dx.doi.org/10.1016/j.net.2018.08.006.

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14

Ni, Muyi, Yong Song, Ming Jin, Jieqiong Jiang, and Qunying Huang. "Design and analysis on tritium system of multi-functional experimental fusion–fission hybrid reactor (FDS-MFX)." Fusion Engineering and Design 87, no. 7-8 (2012): 1004–8. http://dx.doi.org/10.1016/j.fusengdes.2012.02.073.

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15

Zu, Tiejun, Hongchun Wu, Youqi Zheng, Liangzhi Cao, and Chao Yang. "NAPTH: Neutronics analysis code system for the fusion–fission hybrid reactor with pressure tube type blanket." Fusion Engineering and Design 88, no. 3 (2013): 170–76. http://dx.doi.org/10.1016/j.fusengdes.2013.02.014.

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16

Corrêa, Karytha M. S., Natália G. P. L. Oliveira, Claubia Pereira, and Carlos E. Velasquez. "Analysis of reprocessed fuels inserted into a hybrid fusion-fission system based on the ARC reactor." Annals of Nuclear Energy 216 (June 2025): 111291. https://doi.org/10.1016/j.anucene.2025.111291.

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17

Gonfiotti, Bruno, Michela Angelucci, Bradut-Eugen Ghidersa, et al. "Best-Estimate for System Codes (BeSYC): A New Software to Perform Best-Estimate Plus Uncertainty Analyses with Thermal-Hydraulic and Safety System Codes for Both Fusion and Fission Scenarios." Applied Sciences 12, no. 1 (2021): 311. http://dx.doi.org/10.3390/app12010311.

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The development and the validation of old and new software in relevant DEMO reactor conditions have been exploited in the latest years within the EUROfusion Consortium. The aim was to use—if possible—the software already validated for fission reactors and to fill the gaps with new ad-hoc software. As contribution to this effort, the Karlsruhe Institute of Technology (KIT) developed and tested a novel software to apply the Best-Estimate Model Calibration and Prediction through Experimental Data Assimilation methodology to the system codes RELAP5-3D, MELCOR 1.8.6, and MELCOR 2.2. This software i

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18

Bromley, Blair Patrick, and Jude Alexander. "ASSESSMENT OF FAST-SPECTRUM BLANKET LATTICES FOR BREEDING FISSILE FUEL FROM THORIUM AND DEPLETED URANIUM IN AN EXTERNALLY DRIVEN SUB-CRITICAL GAS-COOLED PRESSURE TUBE REACTOR." CNL Nuclear Review 7, no. 2 (2018): 201–20. http://dx.doi.org/10.12943/cnr.2018.00010.

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To ensure long-term nuclear energy security, it is advantageous to consider the use of externally driven sub-critical systems for producing fissile fuel to supply fleets of thermal-spectrum reactors as an alternative to using fast-spectrum or thermal-spectrum breeder reactors. Computational/analytical neutronics and heat transfer studies have been carried out for gas-cooled fuel bundle lattices with mixtures of fertile thorium and depleted uranium (DU) that could be used in the blanket region of a sub-critical fast reactor driven either by a fusion reactor in a hybrid fusion-fission reactor (H

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19

Leung, Ka-Ngo. "New Mini Neutron Tubes with Multiple Applications." Journal of Nuclear Engineering 5, no. 3 (2024): 197–208. http://dx.doi.org/10.3390/jne5030014.

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Recent experimental investigations have demonstrated that a substantial amount of H−/D− ions can be formed by thermal desorption processes. Based on these new findings, new mini axial and coaxial-type neutron tubes have been developed for the production of high or low-energy neutrons via the d-d, d-10B, d-7Li or p-7Li nuclear reactions. By operating these mini neutron tubes with a high frequency AC high-voltage supply, short pulses of high intensity neutron beams can be generated. Multiple applications, such as carbon and well logging, neutron imaging, cancer therapy, medical isotope productio

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20

Knyshev, Vladimir V., Aleksandr G. Karengin, and Igor V. Shamanin. "Subcriticality control elements in a reactor system with an extended plasma source of neutrons with regard for temperature." Nuclear Energy and Technology 7, no. (2) (2021): 97–101. https://doi.org/10.3897/nucet.7.68949.

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Materials have been selected for the shim rods and burnable absorbers to compensate for the excessive reactivity of the facility's blanket part and to provide for the possibility of reactivity control in conjunction with a plasma source of neutrons. Burnable absorber is a layer of zirconium diboride (ZrB<sub>2</sub>) with a thickness of 100 μm applied to the surface of fuel compacts. Boron carbide (B<sub>4</sub>C) rods installed in the helium flow channels and used to bring the entire system into a state with k<sub>eff</sub> = 0.95 have been selected as the shim rod material. Throughout its op

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21

MATSUNAKA, Masayuki, Masayuki OHTA, Hiroyuki MIYAMARU, and Isao MURATA. "Advanced Burnup Calculation Code System in a Subcritical State with Continuous-Energy Monte Carlo Code for Fusion-Fission Hybrid Reactor." Journal of Nuclear Science and Technology 46, no. 8 (2009): 776–86. http://dx.doi.org/10.1080/18811248.2007.9711585.

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22

Xiao, Sicong, Jing Zhao, Zhiwei Zhou, and Yongwei Yang. "Neutronic Study of an Innovative Thorium-Uranium–Based Fusion-Fission Hybrid Energy Reactor with 233U Breeding Enhancement by Using Dual-Coolant System." Fusion Science and Technology 73, no. 4 (2017): 559–67. http://dx.doi.org/10.1080/15361055.2017.1396113.

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23

İpek, Osman. "Analysis of temperature distribution, burn-up and breeding parameters in nuclear fuel rod in fusion-fission reactor system fueled with mixed ThO2-UO2 fuel." International Journal of Energy Research 35, no. 2 (2010): 112–22. http://dx.doi.org/10.1002/er.1771.

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24

Yapici, Hüseyin, Osman İpek, and Mustafa Übeyli. "Investigation of the performance parameters and temperature distribution in fuel rod dependent on operation periods and first wall loads in fusion–fission reactor system fueled with ThO2." Energy Conversion and Management 44, no. 4 (2003): 573–95. http://dx.doi.org/10.1016/s0196-8904(02)00070-5.

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25

Orsitto, F. P., M. Angelone, and M. Tardocchi. "DIAGNOSTICS AND CONTROL OF FUSION-FISSION HYBRID TOKAMAKBASED REACTORS: THE TECHNOLOGY FOR MEASUREMENT SYSTEMS." Problems of Atomic Science and Technology, Ser. Thermonuclear Fusion 44, no. 2 (2021): 78–85. http://dx.doi.org/10.21517/0202-3822-2021-44-2-78-85.

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26

Slugen, Vladimir, Jarmila Degmova, Stanislav Sojak, Martin Petriska, Pavol Noga, and Vladimir Krsjak. "On the Limitations of Positron Annihilation Spectroscopy in the Investigation of Ion-Implanted FeCr Samples." Metals 11, no. 11 (2021): 1689. http://dx.doi.org/10.3390/met11111689.

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New materials for advanced fission/fusion nuclear facilities must inevitably demonstrate resistance to radiation embrittlement. Thermal and radiation ageing accompanied by stress corrosion cracking are dominant effects that limit the operational condition and safe lifetime of the newest nuclear facilities. To study these phenomena and improve the current understanding of various aspects of radiation embrittlement, ion bombardment experiments are widely used as a surrogate for neutron irradiation. While avoiding the induced activity, typical for neutron-irradiated samples, is a clear benefit of

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27

Perry, R. T., and T. A. Parish. "Fusion-Fission Systems with Tritium Producing Fission Reactors." Fusion Technology 8, no. 1P2B (1985): 1057–62. http://dx.doi.org/10.13182/fst85-a39912.

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28

Nishinaka, I., Y. Kasamatsu, M. Tanikawa, S. Goto, and M. Asai. "Radiochemical study of sub-barrier fusion hindrance in the 19F+209Bi reaction." Proceedings in Radiochemistry 1, no. 1 (2011): 117–21. http://dx.doi.org/10.1524/rcpr.2011.0021.

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AbstractProduction cross sections of fission product 99Mo produced in the reaction of 19F + 209Bi have been measured at the incident energies 135–83 MeV near and below the fusion barrier by radiochemical methods. The excitation function for the fusion-fission cross sections in this reaction were deduced down to 80 μb from the measured production cross sections. A systematic analysis of the fusion-fission excitation function shows that sub-barrier fusion hindrance in the heavy mass system 19F + 209Bi is different from that in the medium-heavy mass systems but similar to that in the medium-light

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29

Was, Gary S. "Materials degradation in fission reactors: Lessons learned of relevance to fusion reactor systems." Journal of Nuclear Materials 367-370 (August 2007): 11–20. http://dx.doi.org/10.1016/j.jnucmat.2007.03.008.

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30

Shlenskii, Mikhail, and Boris Kuteev. "System Studies on the Fusion-Fission Hybrid Systems and Its Fuel Cycle." Applied Sciences 10, no. 23 (2020): 8417. http://dx.doi.org/10.3390/app10238417.

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This paper is devoted to applications of fusion-fission hybrid systems (FFHS) as a powerful neutron source implementing transmutation of minor actinides (MA: Np, Am, Cm) extracted from the spent nuclear fuel (SNF) of nuclear reactors. Calculations which simulated nuclide kinetics for the metallic fuel containing MA and neutron transport were performed for particular facilities. Three FFHS with fusion power equal to 40 MW are considered in this study: demo, pilot-industrial and industrial reactors. In addition, needs for a fleet of such reactors are assessed as well as future FFHSs’ impact on R

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31

Vannoni, Alessandra, Pierdomenico Lorusso, Pietro Arena, et al. "STEAM Experimental Facility: A Step Forward for the Development of the EU DEMO BoP Water Coolant Technology." Energies 16, no. 23 (2023): 7811. http://dx.doi.org/10.3390/en16237811.

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Within the EUROfusion roadmap for the technological development of the European-DEMOnstration (EU-DEMO) reactor, a key point has been identified in the discontinuous operation (pulse-dwell-pulse) of the machine. Water Cooled Lithium Lead (WCLL) Breeding Blanket (BB) Primary Heat Transfer Systems (PHTSs) adopt technology and components commonly used in nuclear fission power plants, whose performances could be negatively affected by the above mentioned pulsation, as well as by low-load operation in the dwell phase. This makes mandatory a full assessment of the functional feasibility of such comp

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32

NASIROV, AVAZBEK, GIOVANNI FAZIO, GIORGIO GIARDINA, et al. "COMPARISON OF THE FUSION-FISSION AND QUASIFISSION MECHANISMS IN HEAVY-ION COLLISIONS." International Journal of Modern Physics E 18, no. 04 (2009): 841–49. http://dx.doi.org/10.1142/s021830130901294x.

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The decrease of the evaporation residue yields in reactions with massive nuclei is explained by an increase of the competition between quasifission and complete fusion processes and by the decrease of the survival probability of the heated and rotating nuclei against fission along the de-excitation cascade of the compound nucleus. The experimental data on the yields of evaporation residue, fusion-fission and quasifission fragments in the 48 Ca + 154 Sm reaction are analyzed in the framework of the combined theoretical method based on the dinuclear system concept and advanced statistical model.

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33

Michaillat, Lydie, Tonie Luise Baars, and Andreas Mayer. "Cell-free reconstitution of vacuole membrane fragmentation reveals regulation of vacuole size and number by TORC1." Molecular Biology of the Cell 23, no. 5 (2012): 881–95. http://dx.doi.org/10.1091/mbc.e11-08-0703.

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Size and copy number of organelles are influenced by an equilibrium of membrane fusion and fission. We studied this equilibrium on vacuoles—the lysosomes of yeast. Vacuole fusion can readily be reconstituted and quantified in vitro, but it had not been possible to study fission of the organelle in a similar way. Here we present a cell-free system that reconstitutes fragmentation of purified yeast vacuoles (lysosomes) into smaller vesicles. Fragmentation in vitro reproduces physiological aspects. It requires the dynamin-like GTPase Vps1p, V-ATPase pump activity, cytosolic proteins, and ATP and

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34

Lü Yang, 吕阳, 曾献 Zeng Xian, and 黄洪文 Huang Hongwen. "Nuclear fuel cycle scenarios on fusion-fission hybrid reactor symbiotic systems." High Power Laser and Particle Beams 27, no. 1 (2015): 16003. http://dx.doi.org/10.3788/hplpb20152701.16003.

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35

FAZIO, GIOVANNI, GIORGIO GIARDINA, GIUSEPPE MANDAGLIO, et al. "APPEARANCE OF FAST-FISSION AND QUASI-FISSION IN REACTIONS WITH MASSIVE NUCLEI." Modern Physics Letters A 20, no. 06 (2005): 391–405. http://dx.doi.org/10.1142/s0217732305016671.

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The experimental data on the capture and evaporation residue cross-sections obtained in the 48 Ca +208 Pb reaction were analyzed in the framework of the dynamical model based on the dinuclear system concept and advanced statistical method to clarify the reaction mechanism. The experimental excitation function of the capture reactions was decomposed into contributions of the fusion–fission, quasifission and fast-fission processes. Total evaporation residues and ones after neutron emission were only calculated and compared with the available experimental data.

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36

PAHLAVANI, M. R., D. NADERI та S. M. MIRFATHI. "DYNAMICAL SIMULATION OF γ-RAY MULTIPLICITY IN HEAVY ION FUSION–FISSION REACTIONS BASED ON LANGEVIN EQUATIONS". Modern Physics Letters A 26, № 18 (2011): 1323–30. http://dx.doi.org/10.1142/s0217732311035705.

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In induced fusion–fission reaction, resultant compound system loses a part of its energy via γ-ray emission both before and after scission point that can be measured using proper apparatus. A dynamical Monte Carlo simulation based on the multi-dimensional Langevin equations (L.E) has been applied to obtain γ-ray multiplicity emitted from highly excited compound nucleus. In this study, γ-ray multiplicity has been calculated following the 19 F +232 Th , 12 C +232 Th and 16 O +232 Th reactions. Comparison of calculated results for symmetry and asymmetry fission show γ-ray multiplicity in symmetry

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37

Chirkov, A. Yu. "Hybrid Fusion-Fission System with Neutron Source Based on Deuterium Plasma." Herald of the Bauman Moscow State Technical University. Series Mechanical Engineering, no. 3 (132) (June 2020): 94–104. http://dx.doi.org/10.18698/0236-3941-2020-3-94-104.

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Development of hybrid fusion-fission systems appears today as a promising area in practical use of thermonuclear fusion energy. Thermonuclear plasma in such systems is the source of fast neutrons with the power gain factor Q < 1 power amplification factor in plasma. Hybrid system high amplification is generally achieved through nuclear reactions in the subcritical blanket surrounding plasma. Not only power could be produced in such a blanket, but also nuclear fuel, and waste of the nuclear fuel cycle could be disposed. The problem of systems using the thermonuclear reaction between deuteriu

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38

Tosti, Silvano. "Spontaneity of nuclear fusion: a qualitative analysis via classical thermodynamics." Open Research Europe 1 (August 3, 2021): 67. http://dx.doi.org/10.12688/openreseurope.13738.2.

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Background: So far the feasibility of nuclear reactions has been studied only through the evaluation of the reaction rate, which gives us information about the kinetics, while the thermodynamic analysis has been limited to evaluations of the change in enthalpy without any consideration of the change in entropy. Methods: This work examines the thermodynamics of nuclear fusion reactions through a simplified approach. The analysis introduces the thermodynamic study of fission and fusion reactions through their comparison with a chemical process. Results: The main result is that fission reactions

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39

Tosti, Silvano. "Spontaneity of nuclear fusion: a qualitative analysis via classical thermodynamics." Open Research Europe 1 (June 11, 2021): 67. http://dx.doi.org/10.12688/openreseurope.13738.1.

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Background: So far the feasibility of nuclear reactions has been studied only through the evaluation of the reaction rate, which gives us information about the kinetics, while the thermodynamic analysis has been limited to evaluations of the change in enthalpy without any consideration of the change in entropy. Methods: This work examines the thermodynamics of nuclear fusion reactions through a simplified approach. The analysis introduces the thermodynamic study of fission and fusion reactions through their comparison with a chemical process. Results: The main result is that fission reactions

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40

Tosti, Silvano. "Spontaneity of nuclear fusion: a qualitative analysis via classical thermodynamics." Open Research Europe 1 (October 12, 2021): 67. http://dx.doi.org/10.12688/openreseurope.13738.3.

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Background: So far the feasibility of nuclear reactions has been studied only through the evaluation of the reaction rate, which gives us information about the kinetics, while the thermodynamic analysis has been limited to evaluations of the change in enthalpy without any consideration of the change in entropy. Methods: This work examines the thermodynamics of nuclear fusion reactions through a simplified approach. The analysis introduces the thermodynamic study of fission and fusion reactions through their comparison with a chemical process. Results: The main result is that fission reactions

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41

Kaur, Jagdeep, Amandeep Kaur, Mahinderpal Sharma, Birbikram Singh, and Manjeet Singh Gautam. "Fusion and decay study of Cadmium nucleus formed in Calcium induced reaction at energies lying around the Coulomb barrier." Journal of Physics: Conference Series 2919, no. 1 (2024): 012034. https://doi.org/10.1088/1742-6596/2919/1/012034.

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Abstract The present investigation explores the fusion-fission phenomena in the field of nuclear physics, focusing particularly on their significance in astrophysical research, namely in the nucleosynthesis process occurring in the stars. The present work intends to investigate into the formations and fragmentation mechanisms of 104Cd* system, populated in the interaction of 40Ca and 64Ni ions at energies spanning the mutual electrostatic repulsion. For analysing the formation processes in complete fusion of 40Ca+64Ni channel, the fusion excitation functions are estimated via statistical CCFUL

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42

Götz, Michael, Stefan Götz, Jens-Volker Kratz, et al. "Gas phase synthesis of 4d transition metal carbonyl complexes with thermalized fission fragments in single-atom reactions." Radiochimica Acta 109, no. 3 (2021): 153–65. http://dx.doi.org/10.1515/ract-2020-0052.

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Abstract The formation of carbonyl complexes using atom-at-a-time quantities of short-lived transition metals from fusion and fission reactions was reported in 2012. Numerous studies focussing on this chemical system, which is also applicable for the superheavy elements followed. We report on a novel two-chamber approach for the synthesis of such complexes that allows spatial decoupling of thermalization and gas-phase carbonyl complex synthesis. Neutron induced fission on 235U and spontaneous fission of 248Cm were employed for the production of the fission products. These were stopped inside a

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43

HEINZ, SOPHIE. "CLUSTER EFFECTS IN 25Mg + 206Pb REACTIONS STUDIED WITH THE VELOCITY FILTER SHIP." International Journal of Modern Physics E 17, no. 10 (2008): 2231–34. http://dx.doi.org/10.1142/s0218301308011392.

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Nuclear reaction studies at beam energies of 5.9 and 8.7 × A MeV have been performed with the collision system 25 Mg +206 Pb at the velocity filter SHIP of GSI Darmstadt. The velocity filter offers the possibility to detect the reaction products under zero degree with respect to the beam direction. This allows, together with the measurement of the product velocities, for an identification of the underlying reaction mechanism. Besides fusion-evaporation reactions we found strong signatures for rotation and quasi-fission of nuclear molecules formed after the capture stage in the entrance channel

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Vesely, Ladislav, Vaclav Dostal, and Slavomir Entler. "COMPARISON OF S-CO2 POWER CYCLES FOR NUCLEAR ENERGY." Acta Polytechnica CTU Proceedings 4 (December 16, 2016): 107. http://dx.doi.org/10.14311/ap.2016.4.0107.

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The supercritical carbon dioxide (S-CO<sub>2</sub>) is a possible cooling system for the new generations of nuclear reactors and fusion reactors. The S-CO<sub>2</sub> power cycles have several advantages over other possible coolants such as water and helium. The advantages are the compression work, which is lower than in the case of helium, near the critical point and the S-CO<sub>2</sub> is more compact than water and helium. The disadvantage is so called Pinch point which occurs in the regenerative heat exchanger. The pinch point can be eliminated by an ar

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Grover, Neha, Bhaktima Thakur, and Manoj K. Sharma. "Fragmentation analysis of 88Mo* compound nucleus in view of different decay mechanisms." EPJ Web of Conferences 232 (2020): 03004. http://dx.doi.org/10.1051/epjconf/202023203004.

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In reference to the experimental data, the decay mechanism of 88Mo* compound system formed in 48Ti+40Ca reaction is investigated at three beam energies (Ebeam = 300, 450, and 600 MeV) using the collective clusterization approach of Dynamical Cluster decay Model (DCM). The calculations are done for spherical choice of fragmentation and with the inclusion of quadrupole (β2) deformations having “optimum” orientations. According to the experimental evidence 88Mo* decays via Fusion-Evaporation (FE) and Fusion-Fission (FF) processes, thus the decay cross-sections of this hot and rotating compound sy

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DEUTSCH, CLAUDE, and NAEEM A. TAHIR. "Fusion reactions and matter–antimatter annihilation for space propulsion." Laser and Particle Beams 24, no. 4 (2006): 605–16. http://dx.doi.org/10.1017/s0263034606060691.

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Magnetic confinement fusion (MCF) and inertial confinement fusion (ICF) are critically contrasted in the context of far-distant travels throughout solar system. Both are shown to potentially display superior capabilities for vessel maneuvering at high speed, which are unmatched by standard cryogenic propulsion (SCP). Costs constraints seem less demanding than for ground-based power plants. Main issue is the highly problematic takeoff from earth, in view of safety hazards concomitant to radioactive spills in case of emergency. So, it is recommended to assemble the given powered vessel at high e

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Slough, John. "Suitability of Small Scale Linear Systems for a Fission–Fusion Reactor, Breeder, and Waste Transmutation." Journal of Fusion Energy 27, no. 1-2 (2007): 115–18. http://dx.doi.org/10.1007/s10894-007-9105-2.

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Litnevsky, V. L., F. A. Ivanyuk, G. I. Kosenko, and V. V. Pashkevich. "The fusion of heavy ions within the two step reaction model." Nuclear Physics and Atomic Energy 11, no. 4 (2010): 341–46. https://doi.org/10.15407/jnpae2010.04.341.

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We consider the approaching stage of fusion-fission reactions. The state of the total system is characterised by the three collective parameters: the quadrupole deformations of the target nucleus and the incoming ion and the distance between their centers of mass. We assume "nose to nose" orientation of the projectile and target. The dynamics of the process is described by the Langevin equations for the mentioned above collective parameters. The shell effects of the projectile and target are taken into account in the interaction energy. The numerical calculations are carried out for two reacti

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Tynan, G. R., and A. Abdulla. "How might controlled fusion fit into the emerging low-carbon energy system of the mid-twenty-first century?" Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences 378, no. 2184 (2020): 20200009. http://dx.doi.org/10.1098/rsta.2020.0009.

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We examine the characteristics that fusion-based generation technologies will need to have if they are to compete in the emerging low-carbon energy system of the mid-twenty-first century. It is likely that the majority of future electric energy demand will be provided by the lowest marginal cost energy technology—which in many regions will be stochastically varying renewable solar and wind electric generation coupled to systems that provide up to a few days of energy storage. Firm low-carbon or zero-carbon resources based on gas-fired turbines with carbon capture, advanced fission reactors, hy

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NOMURA, SUEO. "Energy generation from mixing system of nuclear fission/fusion reaction using 6LiD for fuel, etc." Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 39, no. 11 (1997): 962–63. http://dx.doi.org/10.3327/jaesj.39.962.

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