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ArticlePeer ReviewedOpen AccessPlagiarism Passed
Paper ID:IJSREM68676

Experimetal Plasma Confinement in Thermonuclear Fusion Reactors

Stream/Area:

-

Subject:

-

Paper ID:

IJSREM68676

Volume:

10 |

11 |

Nov 2026

Pages:

1-2

Publication Frequency:

Monthly (12 issues per year)

DOI
Digital Object Identifier
10.55041/IJSREM68676

License:International Journal of Scientific Research in Engineering and Management follows the Creative Commons Attribution 4.0 (CC BY 4.0) License, allowing free use and distribution with proper attribution.

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Authors

Dhruv

Dhruv

P.G. Department of Physics

Swami Swatantranand Memorial College Dinanagar

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Abstract

Achieving controlled thermonuclear fusion represents one of the most significant engineering and physics challenges of the 21 st century. Replicating stellar power mechanisms on Earth requires confining deuterium-tritium plasma at temperatures exceeding 100 million °C while satisfying the Lawson Criterion (Lawson, 1957; Godes & Shablov, 2023). This paper examines the primary experimental paradigms of plasma confinement—specifically Magnetic Confinement Fusion (MCF) via tokamaks and stellarators, alongside Inertial Confinement Fusion (ICF). We analyze magnetohydrodynamic (MHD) instabilities, turbulent transport phenomena, and plasma-wall interaction constraints. Furthermore, we review milestones from flagship facilities including ITER, the National Ignition Facility (NIF), and Wendelstein 7-X (IPB Editors et al., 1999; Abu-Shawareb et al., 2024; Klinger et al., 2019), evaluating pathways toward steady-state net energy generation.

KEYWORDS

Inertial Confinement Fusion (ICF). Magnetic Confinement Fusion (MCF

Cite This Article

Dhruv, "Experimetal Plasma Confinement in Thermonuclear Fusion Reactors," International Journal of Scientific Research in Engineering and Management, vol. 10, no. 11, pp. 1-2, Nov 2026. https://doi.org/10.55041/IJSREM68676

Full Article/Conclusion

Laboratory fusion has achieved landmark physics milestones, including laser ignition at NIF (Abu-Shawareb et al., 2024; Danson & Gizzi, 2023) and steady-state optimization at W7-X (Klinger et al., 2019). Realizing commercial fusion power requires advancing tungsten wall survival under 14.1 MeV neutron bombardment, establishing tritium breeding self-sufficiency, and scaling high-temperature superconducting (HTS) magnets.

References

1.   Abu-Shawareb, H., Acree, R., Adams, P., et al. (2024). Achievement oftarget gain larger than unity in an inertial confinement fusion experiment. Physical Review Letters, 132(6), 065102. 2.   Danson, C. N., & Gizzi, L. A. (2023). Inertial confinement fusion ignition achieved at the National Ignition Facility – an editorial. High Power Laser Science and Engineering, 11 , e38. 3.   Godes, A. I., & Shablov, V. L. (2023). Lawson criterion for different scenarios ofusing D-3He fuel in fusion reactors. Nuclear Energy and Technology, 9(3), 207–214. 4.   IPB Editors, ITER Physics Expert Groups, & ITER Joint Central Team. (1999). Chapter 1 : Overview and summary ofthe ITER Physics Basis. Nuclear Fusion, 39(12), 2137–2174. 5.   Klinger, T., Alonso, A., Bohenkov, S., et al. (2019). Performance and properties ofthe first plasmas of Wendelstein 7-X. Plasma Physics and Controlled Fusion, 59(1 ), 014018. 6.   Lawson, J. D. (1957). Some criteria for a power producing thermonuclear reactor. Proceedings ofthe Physical Society. Section B, 70(1 ), 6–10.

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Publication Date

11/2/2026

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Double-Blind Peer Review

Review Rounds: 2

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