مطالعه نقش لایه کَندگی دوتایی کربن‌چگالی‌بالا - پلی استایرن در اشتعال هدف‌های گداخت لختی

ناصریان, مریم; خان بابائی, بابک

doi:10.24200/nst.2023.1375

نوع مقاله : مقاله پژوهشی

نویسندگان

دانشکده فیزیک، دانشگاه دامغان، صندوق پستی: 41167-36716، دامغان، ایران

https://doi.org/10.24200/nst.2023.1375

چکیده

لایه کَندگی کربن‌چگالی‌بالا یکی از گزینه‌های امیدبخش در افروزش گرماهسته‌ای در هدف‌های گداخت محصورشدگی لختی است. به منظور کاهش ناپایداری‌های هیدرودینامیکی و هم‌چنین حفظ سوخت از پدیده پیش‌گرمایش، از طراحی لایه کَندگی دوتایی با لایه بیرونی کربن‌چگالی‌بالا که اخیراً توسط محققین مورد توجه قرار گرفته است، استفاده شده است. از این‌رو در این پژوهش، بهینه‌سازی لایه کَندگی دوتایی یک هدف کروی دلخواه با تک لایه کَندگی پلی‌استایرن را با استفاده از کد هیدرودینامیکی MULTI-IFE مورد بررسی قرار دادیم. این هدف، تحت تابش باریکه‌های متقارن لیزر با طول پالس ns۷_/۲۲، طول موج µm۲۵_/۰ و انرژی کل MJ 7_/1 قرار گرفت. محاسبات ما نشان می‌دهد که ضخامت بهینه کربن‌چگالی‌بالا حدود mm ۶_/۵ است. استفاده از لایه کَندگی دوتایی سبب می‌شود که انرژی لیزر جذب شده در سطح هدف حدود %۸ افزایش یابد. افزایش انرژی جذب شده منجر به افزایش حدود %5 توان آلفای تولیدی شده و در نتیجه کسر مصرف سوخت حدود %۵_/۱ افزایش می‌یابد. در نهایت بهره سوخت حدود %۱۲ افزایش یافت.

کلیدواژه‌ها

عنوان مقاله [English]

Study of thedouble-layerr high-density carbon-polystyrene ablator in the ignition of inertial fusion targets

نویسندگان [English]

M. Naserian
B. Khanbabaei

Department of Physics, Damghan University, P.O. Box: 36716-41167, Damghan - Iran

چکیده [English]

High-density carbon ablator is one of the promising candidates for thermonuclear ignition in inertial confinement fusion. A double-layer polystyrene-high dense carbon ablator has been used to reduce the hydrodynamic instabilities as well as protect the fuel from the preheating phenomenon. Therefore, in this study, we investigated the optimization of a typical double ablator spherical target with an initial polystyrene ablator layer with a thickness of 37 µm by using MULTI-IFE hydrodynamic code. This target was irradiated with symmetrical laser beams with 22.7 ns pulse duration, 0.25 µm wavelength, and 1.7 MJ total pulse energy. Our calculations show that the optimal thickness of the high-density carbon is about 5.6m. Using a diamond ablator increases the absorbed laser energy at the target surface by approximately 8%. Increasing the absorbed energy leads to an increase of about 5% in the alpha power deposition, and as a result, the fuel burn fraction increases by about 1.5%. Eventually, fuel acquire increases by approximately 12%.

کلیدواژه‌ها [English]

Inertial confinement fusion
Central ignition
MULTI-IFE hydrodynamic code
HDC-CH ablator

مراجع

1. C.B. Edwards, et al. Inertial confinement fusion and prospects for power production, High Power Laser Sci. Eng., 3, 1 (2015).

2. R.L. McCrory, et al., Progress in direct-drive inertial confinement fusion, Phys. Plasmas, 15, 055503 (2008).

3. J. Lindl, Development of the indirect‐drive approach to inertial confinement fusion and the target physics basis for ignition and gain, Phys. Plasmas, 2, 3933 (1995).

4. R.L. McCrory, et al, Progress in direct-drive inertial confinement fusion, Phys. Plasmas, 15, 055503 (2008).

5. J. Breil, et al., Multi-material ALE computation in inertial confinement fusion code CHIC, Comput. Fluids, 46, 161 (2011).

6. S. Peng, et al., LARED-Integration code for numerical simulation of the whole process of the indirect-drive laser inertial confinement fusion, High Power Laser and Particle Beams, 27, 032007 (2015).

7. R.W. Paddock, et al., One-dimensional hydrodynamic simulations of low convergence ratio direct-drive inertial confinement fusion implosions, Philos. T. Roy. Soc., A. 379, 20200224 (2020).

8. R. Ramis, J. Meyer-ter-Vehn, MULTI-IFE—A one-dimensional computer code for Inertial Fusion Energy (IFE) target simulations, Comput. Phys. Commun., 203, 226 (2016).

9. S.W. Haan, Point design targets, specifications, and requirements for the 2010 ignition campaign on the National Ignition Facility, Phys. Plasmas, 18, 051001 (2011).

10. J. Nilsen, Understanding the effects of radiative preheat and self-emission from shock heating on equation of state measurement at 100s of Mbar using spherically converging shock waves in a NIF hohlraum, Matter and Radiation at Extremes, 5, 018401 (2020).

11. L.B. Hopkins, et al., Increasing stagnation pressure and thermonuclear performance of inertial confinement fusion capsules by the introduction of a high-Z dopant, Phys. Plasmas, 25, 080706 (2018).

12. V.A. Smalyuk, et al., Hydrodynamic instability growth and mix experiments at the National Ignition Facility, Phys. Plasmas, 21, 056301 (2014).

13. V.A. Smalyuk, et al., Review of hydrodynamic instability experiments in inertially confined fusion implosions on National Ignition Facility, Plasma Phys. Control, 62, 014007 (2020).

14. H. Louis, et al., Miniature Targets for Hydrodynamic Instability Experiments on Nova, Fusion Sci. Technol., 28, 1833 (1995).

15. C. R. Weber, et al., First Measurements of Fuel-Ablator Interface Instability Growth in Inertial Confinement Fusion Implosions on the National Ignition Facility, Phys. Rev. Lett., 117, 159902 (2016).

16. J. Biener, Diamond ablators for inertial confinement fusion, Fusion Sci. Technol., 49, 737 (2006).

17. A.B. Zylstra, et al., Record Energetics for an Inertial Fusion Implosion at NIF, Phys. Rev. Lett., 126, 025001 (2021).

18. L.F.B. Hopkins, et al., First High-Convergence Cryogenic Implosion in a Near-Vacuum Hohlraum, Phys. Rev. Lett., 114, 175001 (2015).

19. J.L. Kline, et al., Progress of indirect drive inertial confinement fusion in the United States, Nuclear Fusion, 59, 11 (2019).

20. X. Qiao, Novel Target Designs to Mitigate Hydrodynamic Instabilities Growth in Inertial Confinement Fusion, Phys. Rev. Lett., 126, 185001 (2021).

21. H.D. Whitley, et al., Comparison of ablators for the polar direct drive exploding pusher platform, High Energy Density Phys, 38, 100928 (2021).

22. R. Ramis, One-dimensional Lagrangian implicit hydrodynamic algorithm form Inertial Confinement Fusion applications, J. Comput. Phys., 330, 173 (2017).

23. R.L. McCrory, C.P. Verdon, Inertial Confinement Fusion, Proceedings of the Course and Workshop, (Eds. Caruso and E. Sindoni, 1988), 83-123.

24. S. Atzeni, J. Meyer-ter-Vehn, The physics of inertial fusion, 1st ed. (Claredon Press, Oxford, 2004).

25. K.S. Kumar, et al., Microwave Assisted Synthesis and Characterizations of Decorated Activated Carbon, Int. J. Electrochem. Sci., 7, 5484 (2012).

26. B.C. Stuart, et al., Nanosecond-to-femtosecond laser-induced breakdown in dielectrics, Phys. Rev., B 53, 4 (1996).

27. B.C. Stuart, et al., Optical ablation by high-power shortpulse lasers, JOSA, B 13, 459 (1996).

28. B. Ali Khan, et al., Femtosecond laser micromachining of diamond: current research status, applications and challenges, Carbon, 179, 209 (2021).

29. V.N. Goncharov, Improving the hot-spot pressure and demonstrating ignition hydrodynamic equivalence in cryogenic deuterium–tritium implosions on OMEGA, Phys. Plasmas, 21, 056315 (2014).

مجله علوم و فنون هسته ای

مطالعه نقش لایه کَندگی دوتایی کربن‌چگالی‌بالا - پلی استایرن در اشتعال هدف‌های گداخت لختی

مراجع

مراجع

1. C.B. Edwards, et al. Inertial confinement fusion and prospects for power production, High Power Laser Sci. Eng., 3, 1 (2015).

2. R.L. McCrory, et al., Progress in direct-drive inertial confinement fusion, Phys. Plasmas, 15, 055503 (2008).

3. J. Lindl, Development of the indirect‐drive approach to inertial confinement fusion and the target physics basis for ignition and gain, Phys. Plasmas, 2, 3933 (1995).

4. R.L. McCrory, et al, Progress in direct-drive inertial confinement fusion, Phys. Plasmas, 15, 055503 (2008).

5. J. Breil, et al., Multi-material ALE computation in inertial confinement fusion code CHIC, Comput. Fluids, 46, 161 (2011).

6. S. Peng, et al., LARED-Integration code for numerical simulation of the whole process of the indirect-drive laser inertial confinement fusion, High Power Laser and Particle Beams, 27, 032007 (2015).

7. R.W. Paddock, et al., One-dimensional hydrodynamic simulations of low convergence ratio direct-drive inertial confinement fusion implosions, Philos. T. Roy. Soc., A. 379, 20200224 (2020).

8. R. Ramis, J. Meyer-ter-Vehn, MULTI-IFE—A one-dimensional computer code for Inertial Fusion Energy (IFE) target simulations, Comput. Phys. Commun., 203, 226 (2016).

9. S.W. Haan, Point design targets, specifications, and requirements for the 2010 ignition campaign on the National Ignition Facility, Phys. Plasmas, 18, 051001 (2011).

10. J. Nilsen, Understanding the effects of radiative preheat and self-emission from shock heating on equation of state measurement at 100s of Mbar using spherically converging shock waves in a NIF hohlraum, Matter and Radiation at Extremes, 5, 018401 (2020).

11. L.B. Hopkins, et al., Increasing stagnation pressure and thermonuclear performance of inertial confinement fusion capsules by the introduction of a high-Z dopant, Phys. Plasmas, 25, 080706 (2018).

12. V.A. Smalyuk, et al., Hydrodynamic instability growth and mix experiments at the National Ignition Facility, Phys. Plasmas, 21, 056301 (2014).

13. V.A. Smalyuk, et al., Review of hydrodynamic instability experiments in inertially confined fusion implosions on National Ignition Facility, Plasma Phys. Control, 62, 014007 (2020).

14. H. Louis, et al., Miniature Targets for Hydrodynamic Instability Experiments on Nova, Fusion Sci. Technol., 28, 1833 (1995).

15. C. R. Weber, et al., First Measurements of Fuel-Ablator Interface Instability Growth in Inertial Confinement Fusion Implosions on the National Ignition Facility, Phys. Rev. Lett., 117, 159902 (2016).

16. J. Biener, Diamond ablators for inertial confinement fusion, Fusion Sci. Technol., 49, 737 (2006).

17. A.B. Zylstra, et al., Record Energetics for an Inertial Fusion Implosion at NIF, Phys. Rev. Lett., 126, 025001 (2021).

18. L.F.B. Hopkins, et al., First High-Convergence Cryogenic Implosion in a Near-Vacuum Hohlraum, Phys. Rev. Lett., 114, 175001 (2015).

19. J.L. Kline, et al., Progress of indirect drive inertial confinement fusion in the United States, Nuclear Fusion, 59, 11 (2019).

20. X. Qiao, Novel Target Designs to Mitigate Hydrodynamic Instabilities Growth in Inertial Confinement Fusion, Phys. Rev. Lett., 126, 185001 (2021).

21. H.D. Whitley, et al., Comparison of ablators for the polar direct drive exploding pusher platform, High Energy Density Phys, 38, 100928 (2021).

22. R. Ramis, One-dimensional Lagrangian implicit hydrodynamic algorithm form Inertial Confinement Fusion applications, J. Comput. Phys., 330, 173 (2017).

23. R.L. McCrory, C.P. Verdon, Inertial Confinement Fusion, Proceedings of the Course and Workshop, (Eds. Caruso and E. Sindoni, 1988), 83-123.

24. S. Atzeni, J. Meyer-ter-Vehn, The physics of inertial fusion, 1st ed. (Claredon Press, Oxford, 2004).

25. K.S. Kumar, et al., Microwave Assisted Synthesis and Characterizations of Decorated Activated Carbon, Int. J. Electrochem. Sci., 7, 5484 (2012).

26. B.C. Stuart, et al., Nanosecond-to-femtosecond laser-induced breakdown in dielectrics, Phys. Rev., B 53, 4 (1996).

27. B.C. Stuart, et al., Optical ablation by high-power shortpulse lasers, JOSA, B 13, 459 (1996).

28. B. Ali Khan, et al., Femtosecond laser micromachining of diamond: current research status, applications and challenges, Carbon, 179, 209 (2021).

29. V.N. Goncharov, Improving the hot-spot pressure and demonstrating ignition hydrodynamic equivalence in cryogenic deuterium–tritium implosions on OMEGA, Phys. Plasmas, 21, 056315 (2014).

30. S. Pfalzner, An Introduction to Inertial Confinement Fusion, (CRC Press, Taylor & Francis, 2006).

31. R.S. Craxton, Direct-drive inertial confinement fusion: A review, Phys Plasmas, 22, 110501 (2015).

دوره 44، شماره 2 - شماره پیاپی 104
تیر 1402
صفحه 116-126

مطالعه نقش لایه کَندگی دوتایی کربن‌چگالی‌بالا - پلی استایرن در اشتعال هدف‌های گداخت لختی

مراجع

مراجع

1. C.B. Edwards, et al. Inertial confinement fusion and prospects for power production, High Power Laser Sci. Eng., 3, 1 (2015).

2. R.L. McCrory, et al., Progress in direct-drive inertial confinement fusion, Phys. Plasmas, 15, 055503 (2008).

3. J. Lindl, Development of the indirect‐drive approach to inertial confinement fusion and the target physics basis for ignition and gain, Phys. Plasmas, 2, 3933 (1995).

4. R.L. McCrory, et al, Progress in direct-drive inertial confinement fusion, Phys. Plasmas, 15, 055503 (2008).

5. J. Breil, et al., Multi-material ALE computation in inertial confinement fusion code CHIC, Comput. Fluids, 46, 161 (2011).

6. S. Peng, et al., LARED-Integration code for numerical simulation of the whole process of the indirect-drive laser inertial confinement fusion, High Power Laser and Particle Beams, 27, 032007 (2015).

7. R.W. Paddock, et al., One-dimensional hydrodynamic simulations of low convergence ratio direct-drive inertial confinement fusion implosions, Philos. T. Roy. Soc., A. 379, 20200224 (2020).

8. R. Ramis, J. Meyer-ter-Vehn, MULTI-IFE—A one-dimensional computer code for Inertial Fusion Energy (IFE) target simulations, Comput. Phys. Commun., 203, 226 (2016).

9. S.W. Haan, Point design targets, specifications, and requirements for the 2010 ignition campaign on the National Ignition Facility, Phys. Plasmas, 18, 051001 (2011).

10. J. Nilsen, Understanding the effects of radiative preheat and self-emission from shock heating on equation of state measurement at 100s of Mbar using spherically converging shock waves in a NIF hohlraum, Matter and Radiation at Extremes, 5, 018401 (2020).

11. L.B. Hopkins, et al., Increasing stagnation pressure and thermonuclear performance of inertial confinement fusion capsules by the introduction of a high-Z dopant, Phys. Plasmas, 25, 080706 (2018).

12. V.A. Smalyuk, et al., Hydrodynamic instability growth and mix experiments at the National Ignition Facility, Phys. Plasmas, 21, 056301 (2014).

13. V.A. Smalyuk, et al., Review of hydrodynamic instability experiments in inertially confined fusion implosions on National Ignition Facility, Plasma Phys. Control, 62, 014007 (2020).

14. H. Louis, et al., Miniature Targets for Hydrodynamic Instability Experiments on Nova, Fusion Sci. Technol., 28, 1833 (1995).

15. C. R. Weber, et al., First Measurements of Fuel-Ablator Interface Instability Growth in Inertial Confinement Fusion Implosions on the National Ignition Facility, Phys. Rev. Lett., 117, 159902 (2016).

16. J. Biener, Diamond ablators for inertial confinement fusion, Fusion Sci. Technol., 49, 737 (2006).

17. A.B. Zylstra, et al., Record Energetics for an Inertial Fusion Implosion at NIF, Phys. Rev. Lett., 126, 025001 (2021).

18. L.F.B. Hopkins, et al., First High-Convergence Cryogenic Implosion in a Near-Vacuum Hohlraum, Phys. Rev. Lett., 114, 175001 (2015).

19. J.L. Kline, et al., Progress of indirect drive inertial confinement fusion in the United States, Nuclear Fusion, 59, 11 (2019).

20. X. Qiao, Novel Target Designs to Mitigate Hydrodynamic Instabilities Growth in Inertial Confinement Fusion, Phys. Rev. Lett., 126, 185001 (2021).

21. H.D. Whitley, et al., Comparison of ablators for the polar direct drive exploding pusher platform, High Energy Density Phys, 38, 100928 (2021).

22. R. Ramis, One-dimensional Lagrangian implicit hydrodynamic algorithm form Inertial Confinement Fusion applications, J. Comput. Phys., 330, 173 (2017).

23. R.L. McCrory, C.P. Verdon, Inertial Confinement Fusion, Proceedings of the Course and Workshop, (Eds. Caruso and E. Sindoni, 1988), 83-123.

24. S. Atzeni, J. Meyer-ter-Vehn, The physics of inertial fusion, 1st ed. (Claredon Press, Oxford, 2004).

25. K.S. Kumar, et al., Microwave Assisted Synthesis and Characterizations of Decorated Activated Carbon, Int. J. Electrochem. Sci., 7, 5484 (2012).

26. B.C. Stuart, et al., Nanosecond-to-femtosecond laser-induced breakdown in dielectrics, Phys. Rev., B 53, 4 (1996).

27. B.C. Stuart, et al., Optical ablation by high-power shortpulse lasers, JOSA, B 13, 459 (1996).

28. B. Ali Khan, et al., Femtosecond laser micromachining of diamond: current research status, applications and challenges, Carbon, 179, 209 (2021).

29. V.N. Goncharov, Improving the hot-spot pressure and demonstrating ignition hydrodynamic equivalence in cryogenic deuterium–tritium implosions on OMEGA, Phys. Plasmas, 21, 056315 (2014).

30. S. Pfalzner, An Introduction to Inertial Confinement Fusion, (CRC Press, Taylor & Francis, 2006).

31. R.S. Craxton, Direct-drive inertial confinement fusion: A review, Phys Plasmas, 22, 110501 (2015).

دوره 44، شماره 2 - شماره پیاپی 104تیر 1402صفحه 116-126

دوره 44، شماره 2 - شماره پیاپی 104
تیر 1402
صفحه 116-126