Skip to main content

Advertisement

SpringerLink
Log in

Advanced Power Conversion Efficiency in Inventive Plasma for Hybrid Toroidal Reactor

  • Original Research
  • Published:
Journal of Fusion Energy Aims and scope Submit manuscript

Abstract

Apex hybrid reactor has a good potential to utilize uranium and thorium fuels in the future. This toroidal reactor is a type of system that facilitates the occurrence of the nuclear fusion and fission events together. The most important feature of hybrid reactor is that the first wall surrounding the plasma is liquid. The advantages of utilizing a liquid wall are high power density capacity good power transformation productivity, the magnitude of the reactor’s operational duration, low failure percentage, short maintenance time and the inclusion of the system’s simple technology and material. The analysis has been made using the MCNP Monte Carlo code and ENDF/B–V–VI nuclear data. Around the fusion chamber, molten salts Flibe (LI2BeF4), lead–lithium (PbLi), Li–Sn, thin-lityum (Li20Sn80) have used as cooling materials. APEX reactor has modeled in the torus form by adding nuclear materials of low significance in the specified percentages between 0 and 12 % to the molten salts. In this study, the neutronic performance of the APEX fusion reactor using various molten salts has been investigated. The nuclear parameters of Apex reactor has been searched for Flibe (LI2BeF4) and Li–Sn, for blanket layers. In case of usage of the Flibe (LI2BeF4), PbLi, and thin-lityum (Li20Sn80) salt solutions at APEX toroidal reactors, fissile material production per source neutron, tritium production speed, total fission rate, energy reproduction factor has been calculated, the results obtained for both salt solutions are compared.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Log in via an institution

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Institutional subscriptions

Fig. 1
Fig. 2
Fig. 3
Fig. 4
Fig. 5
Fig. 6
Fig. 7

Similar content being viewed by others

Abbreviations

R:

Major radius of toroid

r:

(b − R)minor radius of toroid

T6 :

Tritium breeding rate obtained from reaction 6li(n,α)T

T7 :

Tritium breeding rate obtained from Reaction 7Li(n,α,n′)T

TBR: T6 + T7 :

Tritium breeding ratio

MHD:

Magneto hydrodynamic

M:

The energy multiplication factor

∆c:

Atomic density change

∫B·dS = μ0iN:

Amper Laws

\(\Upphi\) :

Neutron flux

References

  1. S. Şahin, M. Übeyli, Modified APEX reactor as a fusion breeder. Energy Convers. Manag.Elsevier 45, 1497–1512 (2004)

    Article  Google Scholar 

  2. R.E. Rognlien, T.D. Rensink, M.E. Smolentsev, S.S.M.Z. Youssef, A. Sawan et al., Fusion reactor design with a liquid first wall and divertor. Fusion Eng. Des. 72, 181–221 (2004)

    Article  Google Scholar 

  3. M. Übeyli, A. Acır, Utilization of thorium in a high power density hybrid reactor with innovative coolants. Energy Convers. Manag. 48, 576–582 (2007)

    Article  Google Scholar 

  4. S. Yalçın, M. Übeyli, A. Acır, Neutronic analysis of a high power density hybrid reactor using innovative coolants. Sadhana Acad. Proc. Eng. Sci. 30(4), 585–600 (2005)

    Google Scholar 

  5. M.A. Abdou, The Apex team, Exploring novel high power density concepts for attractive fusion systems. Fusion Eng. Des. 45, 145–147 (1999)

    Article  Google Scholar 

  6. M.A. Abdou, A. Ying, The APEX team et al., On the exploration of innovative concepts for fusion chamber technology. Fusion Eng. Des. 54, 181–247 (2001)

    Article  Google Scholar 

  7. M.Z. Youssef, ma Abdou, Heat deposition, damage, and tritium breeding characteristic in thick liquid wall lanket concept. Fusion Eng. Des. 49–50, 719–725 (2000)

    Article  Google Scholar 

  8. R.W. Moir, Liquid first walls for a magnetic fusion energy configurations. Nucl. Fusion 37, 557 (1997)

    Article  ADS  Google Scholar 

  9. A. Hançerlioğulları, Determining of energy multiplication in the APEX hybrid reactor by usingThF4 and UF4 heavy metal salts. Int. J. Energy Res. 36(15), 1375–1389 (2012)

    Article  Google Scholar 

  10. B. Şarer, M. Günay, M.E. Korkmaz, A. Hançerlioğulları, Fusion Sci. Technol. 52(1), 107–115 (2007)

    Google Scholar 

  11. J. Bremister, MCNP-4A general monte carlo code N-particle transport code, Version 4A, La-12625 (1993)

Download references

Author information

Authors and Affiliations

  1. Physics Department, Kastamonu Arts and Sciences Faculty, Kastamonu University, 37100, Kastamonu, Turkey

    Aybaba Hançerlioğullari, Mesut Cini & Murat Güdal

Authors
  1. Aybaba Hançerlioğullari
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Mesut Cini
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Murat Güdal
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to Aybaba Hançerlioğullari.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Hançerlioğullari, A., Cini, M. & Güdal, M. Advanced Power Conversion Efficiency in Inventive Plasma for Hybrid Toroidal Reactor. J Fusion Energ 32, 607–614 (2013). https://doi.org/10.1007/s10894-013-9621-1

Download citation

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10894-013-9621-1

Keywords

Search

Navigation