SavedAdd your journal

Journals / Politeknik Dergisi / 2002 / Cilt: 5 - Sayı: 3

$ThF_4$ içeren eriyik tuz kullanılarak ARIES-ST füzyon reaktörünün nötronik olarak incelenmesi

Neutronic investigation of the ARIES-ST fusion reactor by using molten salt with $ThF_4$

Mustafa ÜBEYLİ
Taner ALTINOK
Pages
227–231
DOI
—
🏛️Bibliographic metadata and full text access for this article are provided via DergiPark.
DergiPark Record ↗
✨

AI Summary & Key Takeaways

AI Insight
⚡ TL;DR(Too Long; Didn't Read)

In this hybrid model, a significant amount of fissile fuel can be produced with a fissile fuel breeding ratio of 233U = 0.123 per incident neutron at start-up conditions, which corresponds to 3742 kg 233U/year by a full fusion power of 2740 MW.

📌 3 Key Takeaways

🎯
Objective & Hypothesis:A hybrid modeling of ARIES-ST of the 1000 $MW_el$ power plant is investigated by using molten salt containing $ThF_4$.
📊
Key Findings & Data:Calculations are done by using one-dimensional code of SCALE4.3.
💡
Conclusion & Impact:In this hybrid model, a significant amount of fissile fuel can be produced with a fissile fuel breeding ratio of 233U = 0.123 per incident neutron at start-up conditions, which corresponds to 3742 kg 233U/year by a full fusion power of 2740 MW.
🔬Design:Modeling & Simulation
📍Scope:Comprehensive Sample
⚙️Variables:Domain Parameters

Abstract

A hybrid modeling of ARIES-ST of the 1000 $MW_el$ power plant is investigated by using molten salt containing $ThF_4$. Calculations are done by using one-dimensional code of SCALE4.3. Tritium breeding ratio is greater than 1.05 so that tritium self-sufficiency is maintained for DT fusion driver. In this hybrid model, a significant amount of fissile fuel can be produced with a fissile fuel breeding ratio of 233U = 0.123 per incident neutron at start-up conditions, which corresponds to 3742 kg 233U/year by a full fusion power of 2740 MW.

Özet

$ThF_4$ içeren eriyik tuz kullanarak 1000 $MW_el$ gücündeki ARIES-ST reaktörünün hibrid modellenmesi incelenmiştir. Hesaplamalar tek boyutlu SCALE4.3 kodu kullanılarak yapılmıştır. Trityum üretim oranı l .05'den büyüktür ve bundan dolayı DT füzyon kaynağı için trityumun kendi kendine yeterli olması sağlanmaktadır. Bu hibrid modelde, önemli miktarda fisil yakıt üretilebilecektir. Başlangıç şartlarındaki nötron başına fısil yakıt üretim oranı 233U = 0.123'tür ve bu da 2740 MW'lık tam füzyon gücü altında 3742 kg 233U/yıl demektir.

🔖

Cite This Article

ÜBEYLİ, M., ALTINOK, T. (2002). $ThF_4$ içeren eriyik tuz kullanılarak ARIES-ST füzyon reaktörünün nötronik olarak incelenmesi. Politeknik Dergisi, Cilt: 5 - Sayı: 3, 227–231. https://ajindex.com/articles/306941

References (15)

  1. Mogahed, E.A., and the ARIES Team, Loss of Coolant Accident (LOCA) Analysis of the ARIES-ST Design, 1.3th Topical Meeting on the Technology of Fusion Energy, June 7-11, 1998, Nashville TN
  2. ARIES Team, Tillack, M.S., Wang, X.R., Pulsifer, J., Malang, S., Sze, D.K., ARIES-ST Breeding Blanket Design and Analysis, Fusion Engineering and Design, vol. 49-50, pp. 689- 695, 2000
  3. Sze, D.K., et al., Blanket System Selection for the ARIES-ST, Fusion Engineering and Design, vol. 48, pp. 371-378, 2000
  4. El-Guebaly, L.A., and The ARIES Team, Three-Dimensional Neutronics Study for ARIES-St Power Plant, 13th Topical Meeting on the Technology of Fusion Energy, June 7- 11, 1998, Nashville TN
  5. El-Guebaly, L.A., et al., Need for inboard Shield to Protect the Center Post of ST Power Plants, 13th Topical Meeting on the Technology of Fusion Energy, June 7-11, 1998, Nashville TN
  6. Yapıcı, H., Übeyli, M., Yalçın, Ş, Neutronic Analysis of Prometheus Reactor Fuelled with Various Compounds of Thorium and Uranium, Annals of Nuclear Energy, (to be published)
  7. Şahin, S., et al.,Neutronic Investigation of a Hybrid Version of the ARIES-RS fusion reactor, Annals of Nuclear Energy, (submitted)
  8. Fetter, S., Cheng, E.T., Mann, F.M., (1988). Long-Term Radioactivity in Fusion Reactors, Fusion Engineering and Design, 6, 123
  9. Jordan W. C., S. M. Bowman, Scale Cross- Section Libraries, NUREG/CR-0200, Revision 5, 3, section M4, ORNL/NUREG/CSD-2/V3/ R5, Oak Ridge National Laboratory, 1997
  10. Greene N. M., L. M. Petrie, XSDRNPM, A One-Dimensional Discrete-Ordinates Code For Transport Analysis, NUREG/CR-0200, Revision 5, 2, Section F3, ORNL/ NUREG/ CSD-2/V2/R5, Oak Ridge National Laboratory, 1997
  11. Şahin, S., Radiation Shielding Calculations For Fast Reactors (in Turkish), Gazi University, Publication # 169, Faculty of Science and Literature, Publication number 22, Ankara, Turkey, 1991
  12. Yapıcı, H., XSCALC for Interfacing Output of XSDRN to Calculate Integral Neutronic Data, Erciyes University, Kayseri, TURKEY, 2001
  13. Greene N. M., BONAMI, Resonance Self- Shielding By The Bondarenko Method, NUREG/CR-0200, Revision 5, 2, section F1, ORNL/NUREG/CSD-2/V2/R5, Oak Ridge National Laboratory, 1997
  14. Greene N. M., L. M. Petrie, R. M. Westfall, NITAWL-II, Scale System Module For Performing Resonance Shielding and Working Library Production, NUREG / CR-0200, Revision 5, 2, Section F2, ORNL/NUREG/ CSD-2/V2/R5,Oak Ridge National Laboratory, 1997
  15. Landers N. F., L. M. Pe