Journals / Gazi University Journal of Science / 2003 / Cilt: 16 - Sayı: 2

FISSILE FUEL BREEDING IN THE ARIES-ST FUSION REACTOR BY USING MOLTEN SALT WITH UF4

Pages
387–394
Publication Date
2010-08-06
DOI
—
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AI Summary & Key Takeaways

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⚡ TL;DR(Too Long; Didn't Read)

Key Words: ARIES-ST fusion reactor, molten salt, fissile fuel breeding.

📌 3 Key Takeaways

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Objective & Hypothesis:ABSTRACTFissile fuel breeding in the ARIES-ST of the 1000 MWel power plant is investigated by using molten salt containing UF4 Calculations are done with the aid of one-dimensional code of SCALE4.3.
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Key Findings & Data:In this hybrid model, a substantial amount of fissile fuel can be produced with a fissile fuel breeding ratio of 239 Pu = 0.115 per incident neutron at start-up conditions, that corresponds to 3558 kg 239 Pu/year by a full fusion power of 2740 MW.
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Conclusion & Impact:Key Words: ARIES-ST fusion reactor, molten salt, fissile fuel breeding.
🔬Design:Modeling & Simulation
📍Scope:Comprehensive Sample
⚙️Variables:ARIES-ST fusion reactor · molten salt · fissile fuel breeding.

Abstract

ABSTRACTFissile fuel breeding in the ARIES-ST of the 1000 MWel power plant is investigated by using molten salt containing UF4 Calculations are done with the aid of one-dimensional code of SCALE4.3. In this hybrid model, a substantial amount of fissile fuel can be produced with a fissile fuel breeding ratio of 239 Pu = 0.115 per incident neutron at start-up conditions, that corresponds to 3558 kg 239 Pu/year by a full fusion power of 2740 MW. Tritium breeding ratio is found as 1.14 so that tritium self-sufficiency is maintained for DT fusion driver. Key Words: ARIES-ST fusion reactor, molten salt, fissile fuel breeding.

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Cite This Article

ÜBEYLİ, M. (2010). FISSILE FUEL BREEDING IN THE ARIES-ST FUSION REACTOR BY USING MOLTEN SALT WITH UF4. Gazi University Journal of Science, Cilt: 16 - Sayı: 2, 387–394. https://ajindex.com/articles/255482

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