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Journals / Politeknik Dergisi / 2007 / Cilt: 10 - Sayı: 3

Impact of various reflector materials on the neutronic performance of a fusion-fission hybrid reactor with $ThO_2$ fuel

$ThO_2$ yakıtlı bir füzyon-fisyon hibrid reaktöründe farklı reflektör malzemelerinin nötronik performansa etkisi

Adem ACIR
Pages
263–270
DOI
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AI Summary & Key Takeaways

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

As a result, these candidate reflector materials could be used in hybrid reactors to improve the neutronic performances.

📌 3 Key Takeaways

🎯
Objective & Hypothesis:Reflector materials were performed in the fusion-fission reactor design to enhance the blanket performance and to eliminate the main disadvantage of this blanket concept.
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Key Findings & Data:In this study, to improve the neutronic performance of the fusion-fission hybrid reactor with ThO2, various reflector materials, namely, graphite (C), Zirconium Hydride (ZrH2), Titanium Carbide (TiC) and Zirconium Carbide (ZrC) were investigated.
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Conclusion & Impact:As a result, these candidate reflector materials could be used in hybrid reactors to improve the neutronic performances.
🔬Design:Survey & Empirical Study
📍Scope:Comprehensive Sample
⚙️Variables:Domain Parameters

Abstract

Reflector materials were performed in the fusion-fission reactor design to enhance the blanket performance and to eliminate the main disadvantage of this blanket concept. In this study, to improve the neutronic performance of the fusion-fission hybrid reactor with ThO2, various reflector materials, namely, graphite (C), Zirconium Hydride (ZrH2), Titanium Carbide (TiC) and Zirconium Carbide (ZrC) were investigated. The neutron wall load was taken at 5 MW/m2 and SS-304 alloy was used in the first wall. And also $Li_{17}Pb_{83}$ eutectic lithium was utilized for coolant in the fuel zone to supply heat transfer out of the blanket. 14.1 MeV D-T neutron source were used as a fusion neutron source. Neutron transport calculations were done with the aid of one dimensional computer system code of SCALE 5. Among the investigated reflector materials, graphite and ZrH2 showed better tritium breeding ratio (TBR) than others whereas ZrC had the worst performance. ZrH2 was determided the best neutron shielding because of minimal neutron leakage from the blanket. On the other hand, while ZrC showed better fissile fuel breeding, ZrH2 had the worst performance. As a result, these candidate reflector materials could be used in hybrid reactors to improve the neutronic performances.

Özet

Reflektör malzemeler, manto performansını artırmak ve manto yapısındaki dezavantajları ortadan kaldırmak amacıyla füzyon-fisyon reaktör yapısında incelenmiştir. Bu çalışmada, ThO2 yakıtlı bir füzyon-fisyon hibrid reaktöründe çeşitli reflektör malzemeler, sırasıyla, Carbon (C) Zirkonyum hidrür (ZrH2), Titanyum karbür (TiC) ve Zirkonyum karbür (ZrC) kullanılarak reaktörün nötronik performansını düzgünleştirmek amacıyla araştırılmıştır. Nötron yükü 5 MW/m2 alınmış ve ilk duvar yapı malzemesi olarak SS-304 kullanılmıştır. Ayrıca, blanketteki ısıyı transfer etmek amacıyla yakıt bölgesinde $Li_{17}Pb_{83}$ ötektik lityum soğutucu seçilmiştir. Füzyon nötron kaynağı olarak 14.1 MeV ortalama enerjili D-T nötron kaynağı kullanılmıştır. Nötron transport hesaplamaları, tek boyutlu SCALE 5 bilgisayar sistem kodu yardımıyla yapılmıştır. Araştırılan reflektör malzemeler arasında, trityum üretim performansı açısından grafit karbon ve ZrH2 diğer reflektör malzemelerine göre en iyi performansı gösterirken, ZrC en kötü performansı göstermiştir. ZrH2, blanketteki en az nötron kaçağından dolayı ZrH2 en iyi nötron zırhlama malzemesi olarak belirlenmiştir. Öte yandan ZrC en iyi fisil yakıt üretimini gösterirken, ZrH2 en kötü performansı vermiştir. Sonuç olarak, bu aday reflektör malzemeleri hibrid reaktörlerde nötronik performansı düzgünleştirmek amacıyla kullanılabilecektir.

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Cite This Article

ACIR, A. (2007). Impact of various reflector materials on the neutronic performance of a fusion-fission hybrid reactor with $ThO_2$ fuel. Politeknik Dergisi, Cilt: 10 - Sayı: 3, 263–270. https://ajindex.com/articles/306806

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