Investigation of the effect using different coolant on the performance of a Tokamak Fusion Reactor blanket
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Date
2020
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Turkish Energy, Nuclear and Mineral Research Agency
Abstract
Bu çalışmada, ilk duvar yükü 5 MW/m2 (2.22 x 1014 n/s) ve 500 MW füzyon gücü için üç-boyutlu TOROID yapıya sahip geometrili bir manyetik füzyon reaktör modellemesi yapılmıştır. Modellenen füzyon reaktöründe, plazma bölgesinde D-T yakıtı kullanılmıştır. Beş farklı model kapsamında, ilk duvar bölgesinde 1DS-ODS çeliği ve reaktörün soğutucu bölgesinde Flibe (LiF-BeF), Flina (LiF-NaF), Flinak (LiF-NaF-KF) Flinabe (LiF-NaF-BeF) ve Li malzemeleri kullanılmıştır. Bu çalışmanın ilk aşamasında, beş farklı soğutma malzemesi için trityum üretim oranı (TBR), enerji çoğaltım faktörü (M) ve ısı akısı hesaplanmıştır. Çalışmanın ikinci aşamasında, ilk duvardaki ısı akısı ve gaz üretimi ile atom başına kayma (DPA) değerleri ve mıknatıs tabakasındaki nükleer ısı üretimi Monte Carlo nötron ‐ foton transport bilgisayar kodu (MCNP5) yardımıyla ENDF/B‐VI ve CLAW‐IV olarak adlandırılan nükleer bilgi kütüphaneleri kullanılarak hesaplanmıştır. İncelenen modellere göre, TBR ve M değerlerinin reaktöründe üretilen soğutucu malzeme içindeki lityum izotoplarının yoğunluğu ile doğrudan orantılı olduğu gözlenmiştir. Yüksek nötron yoğunluğuna sahip tüm modellerde, füzyon reaktörlerin çalışması için gereken minimum TBR (≥1.05) değeri elde edilmiştir. Bu değerlendirmeler sonucunda, soğutucu olarak lityum ve Flibe içeren modeller en iyi nötronik performansı göstermiştir.
In this study, magnetic fusion reactor modeling with three-dimensional TOROID structure geometry has been completed for the first wall load 5 MW/m2 (2.22 x 1014 n/s) and 500 MW fusion power. In the modeled fusion reactor, D-T fuel was used in the plasma region. Within the scope of five different models, 1DS-ODS steel in the first wall region and Flibe (LiF-BeF), Flina (LiF-NaF), Flinak (LiF-NaF-KF) Flinabe (LiF-NaF-BeF) and Li materials were used in the cooling zone of the reactor. In the first stage of this study, tritium breeding ratio (TBR), energy multiplication factor (M) and heat flux of the reactor were calculated for five different cooling materials. In the second stage of the study heat flux gas production and displacement per atoms (DPA) values in the first wall region and nuclear heat generation in the magnet layer were calculated by using Monte Carlo methods with Monte Carlo neutron‐photon transport code (MCNP5) and nuclear data libraries named as ENDF/B‐VI and CLAW‐IV. According to investigated models, it was observed that the density of lithium isotopes in the coolant material and produced in the reactor TBR and M were directly proportional. In all models with high neutron density, the minimum TBR (≥1.05) required for the operation of the reactors was obtained. In this context, the models which contains lithium and Flibe as coolants, they showed the best neutronic performance according to all considerations.
In this study, magnetic fusion reactor modeling with three-dimensional TOROID structure geometry has been completed for the first wall load 5 MW/m2 (2.22 x 1014 n/s) and 500 MW fusion power. In the modeled fusion reactor, D-T fuel was used in the plasma region. Within the scope of five different models, 1DS-ODS steel in the first wall region and Flibe (LiF-BeF), Flina (LiF-NaF), Flinak (LiF-NaF-KF) Flinabe (LiF-NaF-BeF) and Li materials were used in the cooling zone of the reactor. In the first stage of this study, tritium breeding ratio (TBR), energy multiplication factor (M) and heat flux of the reactor were calculated for five different cooling materials. In the second stage of the study heat flux gas production and displacement per atoms (DPA) values in the first wall region and nuclear heat generation in the magnet layer were calculated by using Monte Carlo methods with Monte Carlo neutron‐photon transport code (MCNP5) and nuclear data libraries named as ENDF/B‐VI and CLAW‐IV. According to investigated models, it was observed that the density of lithium isotopes in the coolant material and produced in the reactor TBR and M were directly proportional. In all models with high neutron density, the minimum TBR (≥1.05) required for the operation of the reactors was obtained. In this context, the models which contains lithium and Flibe as coolants, they showed the best neutronic performance according to all considerations.
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Keywords
Magnetic fusion reactor, Manyetik füzyon reaktörü, Energy multiplication factor, Enerji çoğaltım faktörü, Gas production, Gaz üretimi, TBR, DPA
Citation
Şahin, H. M. ve Karakoç, A. (2020). Investigation of the effect using different coolant on the performance of a Tokamak Fusion Reactor blanket. Turkish Journal of Nuclear Sciences, 32(1), 59-72.