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Refinado por: Nome da Publicação: Nuclear Engineering And Design remover
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1
Study on the mass and heat transfer characteristics of the drying process of spent nuclear fuel cladding with nitrogen assisted
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Study on the mass and heat transfer characteristics of the drying process of spent nuclear fuel cladding with nitrogen assisted

Wang, Weibing ; Wang, Bo ; Zhou, Ying ; Wang, Shengnan ; Zhang, Meng

Nuclear engineering and design, 2022-05, Vol.391, p.111672, Article 111672 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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2
Development of MPS method and analytical approach for investigating RPV debris bed and lower head interaction in 1F Units-2 and 3
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Development of MPS method and analytical approach for investigating RPV debris bed and lower head interaction in 1F Units-2 and 3

Takahashi, Nozomu ; Duan, Guangtao ; Yamaji, Akifumi ; Li, Xin ; Sato, Ikken

Nuclear engineering and design, 2021-08, Vol.379, p.111244, Article 111244 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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3
Self-welding of Inconel 617 under high-pressure-high-temperature conditions for nuclear reactors
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Self-welding of Inconel 617 under high-pressure-high-temperature conditions for nuclear reactors

Zheng, Yong ; Rahman, Md Saifur ; Polycarpou, Andreas A.

Nuclear engineering and design, 2021-01, Vol.371 (C), p.110941, Article 110941 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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4
Modeling and analysis of molten fuel vaporization and expansion for a sodium fast reactor severe accident
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Modeling and analysis of molten fuel vaporization and expansion for a sodium fast reactor severe accident

Manchon, X. ; Bertrand, F. ; Marie, N. ; Lance, M. ; Schmitt, D.

Nuclear engineering and design, 2017-10, Vol.322, p.522-535 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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5
Transient heat exchanges under fast Reactivity-Initiated Accident
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Transient heat exchanges under fast Reactivity-Initiated Accident

Labit, J.-M. ; Marie, N. ; Clamens, O. ; Merle, E.

Nuclear engineering and design, 2021-03, Vol.373, p.110917, Article 110917 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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6
Review of the nuclear reactor thermal hydraulic research in ocean motions
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Review of the nuclear reactor thermal hydraulic research in ocean motions

Yan, B.H.

Nuclear engineering and design, 2017-03, Vol.313, p.370-385 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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7
Fork-end heat pipe for passive air cooling of spent nuclear fuel pool
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Fork-end heat pipe for passive air cooling of spent nuclear fuel pool

Choi, Jonghwi ; Lim, Changhwan ; Kim, Hyungdae

Nuclear engineering and design, 2021-04, Vol.374, p.111081, Article 111081 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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8
Study on dryout and rewetting during accidents including ATWS for the BWR at JAEA
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Study on dryout and rewetting during accidents including ATWS for the BWR at JAEA

Satou, A. ; Wada, Y. ; Sibamoto, Y. ; Yonomoto, T.

Nuclear engineering and design, 2019-12, Vol.354, p.110164, Article 110164 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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9
A review of correlations to model the packing structure and effective thermal conductivity in packed beds of mono-sized spherical particles
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A review of correlations to model the packing structure and effective thermal conductivity in packed beds of mono-sized spherical particles

van Antwerpen, W. ; du Toit, C.G. ; Rousseau, P.G.

Nuclear engineering and design, 2010-07, Vol.240 (7), p.1803-1818 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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10
Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor
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Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor

Tian, Zhixing ; Liu, Xiao ; Wang, Chenglong ; Zhang, Dalin ; Tian, Wenxi ; Qiu, Suizheng ; Su, G.H.

Nuclear engineering and design, 2021-07, Vol.378, p.111182, Article 111182 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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