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Refinado por: Nome da Publicação: Journal of Nuclear Materials remover
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A laboratory-scale process for producing dilithium beryllium tetrafluoride (FLiBe) with dissolved uranium tetrafluoride
A laboratory-scale process for producing dilithium beryllium tetrafluoride (FLiBe) with dissolved uranium tetrafluoride
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A laboratory-scale process for producing dilithium beryllium tetrafluoride (FLiBe) with dissolved uranium tetrafluoride

Scheele, Randall D. ; Okabe, Parker K. ; McNamara, Bruce K. ; Sinkov, Sergey I. ; Sorensen, Kirk F.

Journal of nuclear materials, 2023-11, Vol.585, p.154636, Article 154636 [Periódico revisado por pares]

Elsevier B.V

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2
Interaction of beryllium with 316H stainless steel in molten Li2BeF4 (FLiBe)
Interaction of beryllium with 316H stainless steel in molten Li2BeF4 (FLiBe)
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Interaction of beryllium with 316H stainless steel in molten Li2BeF4 (FLiBe)

Keiser, James R ; Singh, Preet M ; Lance, Michael J. ; Meyer, Harry M. ; Myhre, Kristian G. ; Lowe, Tracie M. ; Sulejmanovic, Dino ; Cakmak, Ercan ; Cox, Victoria A. ; Hawkins, C. Shane ; Willoughby, Adam W.

Journal of nuclear materials, 2022-07, Vol.565 (July), p.153698, Article 153698 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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3
The role of grain boundaries and denuded zones for tritium retention in high-dose neutron irradiated beryllium
The role of grain boundaries and denuded zones for tritium retention in high-dose neutron irradiated beryllium
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The role of grain boundaries and denuded zones for tritium retention in high-dose neutron irradiated beryllium

Zimber, N. ; Vladimirov, P.

Journal of nuclear materials, 2022-09, Vol.568, p.153855, Article 153855 [Periódico revisado por pares]

Elsevier B.V

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4
Fabrication of Beryllium Oxide Based Fully Ceramic Microencapsulated Nuclear Fuels with Dispersed TRISO Particles by Pressureless Sintering Method
Fabrication of Beryllium Oxide Based Fully Ceramic Microencapsulated Nuclear Fuels with Dispersed TRISO Particles by Pressureless Sintering Method
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Fabrication of Beryllium Oxide Based Fully Ceramic Microencapsulated Nuclear Fuels with Dispersed TRISO Particles by Pressureless Sintering Method

Zhou, Xiang-wen ; Hou, Ming-dong ; Liu, Rongzheng ; Liu, Bing

Journal of nuclear materials, 2024-01, Vol.588, p.154798, Article 154798 [Periódico revisado por pares]

Elsevier B.V

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5
Tritium release and retention in beryllium pebbles irradiated up to 640 appm tritium and 6000 appm helium
Tritium release and retention in beryllium pebbles irradiated up to 640 appm tritium and 6000 appm helium
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Tritium release and retention in beryllium pebbles irradiated up to 640 appm tritium and 6000 appm helium

Chakin, Vladimir ; Rolli, Rolf ; Klimenkov, Michael ; Zmitko, Milan

Journal of nuclear materials, 2020-12, Vol.542, p.152521, Article 152521 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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6
Copper-doped beryllium and beryllium oxide interface: A first-principles study
Copper-doped beryllium and beryllium oxide interface: A first-principles study
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Copper-doped beryllium and beryllium oxide interface: A first-principles study

Liu, Yu ; Liu, Xiaohui ; Chen, Mohan

Journal of nuclear materials, 2021-03, Vol.545, p.152733, Article 152733 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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7
Structural properties and thermal decomposition kinetics of beryllium deuteride by isotope exchange: Compared to beryllium hydride
Structural properties and thermal decomposition kinetics of beryllium deuteride by isotope exchange: Compared to beryllium hydride
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Structural properties and thermal decomposition kinetics of beryllium deuteride by isotope exchange: Compared to beryllium hydride

Jin, Lei ; Luo, Jiangshan ; Zhang, Jiqiang ; He, Yudan ; Chen, Long ; Luo, Bingchi ; Li, Kai ; Li, Wenqi ; Zhang, Yingjuan ; Wu, Weidong

Journal of nuclear materials, 2018-10, Vol.509, p.9-14 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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8
Deuterium desorption and retention of Beryllium intermetallic compounds for fusion applications
Deuterium desorption and retention of Beryllium intermetallic compounds for fusion applications
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Deuterium desorption and retention of Beryllium intermetallic compounds for fusion applications

Kim, Jae-Hwan ; Hwang, Taehyun ; Nakano, Suguru ; Miyamoto, Mitsutaka ; Iwakiri, Hirotomo ; Nakamichi, Masaru

Journal of nuclear materials, 2021-07, Vol.550, p.152936, Article 152936 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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9
A novel method to stably secure beryllium resources for fusion blankets
A novel method to stably secure beryllium resources for fusion blankets
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A novel method to stably secure beryllium resources for fusion blankets

Kim, Jae-Hwan ; Nakano, Suguru ; Nakamichi, Masaru

Journal of nuclear materials, 2020-12, Vol.542, p.152522, Article 152522 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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10
Development and application of a microstructure dependent thermal resistor model for UO2 reactor fuel with high thermal conductivity additives
Development and application of a microstructure dependent thermal resistor model for UO2 reactor fuel with high thermal conductivity additives
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Development and application of a microstructure dependent thermal resistor model for UO2 reactor fuel with high thermal conductivity additives

Hilty, Floyd W. ; Tonks, Michael R.

Journal of nuclear materials, 2020-11, Vol.540, p.152334, Article 152334 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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