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نمایش تعداد 1-10 از 13

Fusion Licensing and Safety Studies in Korea

نوع: Journal Paper

نویسنده : Hyuck Jong Kim; Hyung Chan Kim; Myeun Kwon; Gyunyoung Heo; In-Ju Hwang; Soon Heung Chang; Jong Kyung Kim; Yong Su Kim

ناشر: IEEE

سال: 2014

Liquid Metal MHD Flows Near Noninsulated Gaps Between Flow Channel Inserts in DCLL Blankets

نوع: Journal Paper

نویسنده : Buhler, Leo; Mistrangelo, Chiara

ناشر: IEEE

سال: 2014

Comparison of Possible Flow Distribution Systems for PbLi Self-Cooled Blankets With Respect to MHD, Fabrication, and Maintenance

نوع: Journal Paper

نویسنده : Koehly, C.; Tillack, M.S.; Wang, X.R.; Najmabadi, Farrokh; Malang, S.

ناشر: IEEE

سال: 2014

Scoping Study on In-Vessel LOCA of a Korean TBS in ITER

نوع: Journal Paper

نویسنده : Hyung Gon Jin; Dong Won Lee; Eo Hwak Lee; Suk Kwon Kim; Jae Sung Yoon; Moo Yung Ahn; Seung Yon Cho

ناشر: IEEE

سال: 2014

Instrumentation for Neutron Flux and Tritium Production Rate Monitoring in the European TBM in ITER

نوع: Journal Paper

نویسنده : Klix, Axel; Angelone, M.; Fischer, Ulrich; Gehre, Daniel; Kleizer, Gabor; Lyoussi, A.; Ruecker, Tom; Rovni, Istvan; Szalkai, Dora

ناشر: IEEE

سال: 2014

Buoyant-MHD Flows in HCLL Blankets Caused by Spatially Varying Thermal Loads

نوع: Journal Paper

نویسنده : Mistrangelo, Chiara; Buhler, Leo; Aiello, Giovanni

ناشر: IEEE

سال: 2014

Nuclear Aspects and Blanket Testing/Development Strategy for ST-FNSF

نوع: Journal Paper

نویسنده : El-Guebaly, L.; Mynsberge, L.; Menard, J.; Brown, Tyler; Malang, S.; Waganer, Lester

ناشر: IEEE

سال: 2014

Contact Stress Evaluation Based on Thermal-Structural Analysis in KO HCCR TBM Submodules for ITER

نوع: Journal Paper

نویسنده : Kyu In Shin; Dong Won Lee; Hyung Gon Jin; Eo Hwak Lee; Suk-Kwon Kim; Jae Sung Yoon; Mu-Young Ahn; Seungyon Cho

ناشر: IEEE

سال: 2014

Tritium Transport Issues for Helium-Cooled Breeding Blankets

نوع: Journal Paper

نویسنده : Franza, F.; Boccaccini, Lorenzo V.; Demange, D.; Ciampichetti, A.; Zucchetti, M.

ناشر: IEEE

سال: 2014

Investigation on the Possibility of Tritium Self-Sufficiency for CFETR Using a PWR Water-Cooled Blanket

نوع: Journal Paper

نویسنده : Changle Liu; Damao Yao; Xiang Gao; Zhaoliang Wang; Chao Liang; Zibo Zhou; Lei Cao; Tiejun Xu

ناشر: IEEE

سال: 2014

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Fusion Licensing and Safety Studies in Korea

Liquid Metal MHD Flows Near Noninsulated Gaps Between Flow Channel Inserts in DCLL Blankets

Comparison of Possible Flow Distribution Systems for PbLi Self-Cooled Blankets With Respect to MHD, Fabrication, and Maintenance

Scoping Study on In-Vessel LOCA of a Korean TBS in ITER

Instrumentation for Neutron Flux and Tritium Production Rate Monitoring in the European TBM in ITER

Buoyant-MHD Flows in HCLL Blankets Caused by Spatially Varying Thermal Loads

Nuclear Aspects and Blanket Testing/Development Strategy for ST-FNSF

Contact Stress Evaluation Based on Thermal-Structural Analysis in KO HCCR TBM Submodules for ITER

Tritium Transport Issues for Helium-Cooled Breeding Blankets

Investigation on the Possibility of Tritium Self-Sufficiency for CFETR Using a PWR Water-Cooled Blanket

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Fusion Licensing and Safety Studies in Korea

Liquid Metal MHD Flows Near Noninsulated Gaps Between Flow Channel Inserts in DCLL Blankets

Comparison of Possible Flow Distribution Systems for PbLi Self-Cooled Blankets With Respect to MHD, Fabrication, and Maintenance

Scoping Study on In-Vessel LOCA of a Korean TBS in ITER

Instrumentation for Neutron Flux and Tritium Production Rate Monitoring in the European TBM in ITER

Buoyant-MHD Flows in HCLL Blankets Caused by Spatially Varying Thermal Loads

Nuclear Aspects and Blanket Testing/Development Strategy for ST-FNSF

Contact Stress Evaluation Based on Thermal-Structural Analysis in KO HCCR TBM Submodules for ITER

Tritium Transport Issues for Helium-Cooled Breeding Blankets

Investigation on the Possibility of Tritium Self-Sufficiency for CFETR Using a PWR Water-Cooled Blanket