Properties

Pinto, N.P.

doi:10.1007/978-1-4757-0668-0_16

Cited by 12 publications

(3 citation statements)

References 20 publications

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“…With so much data available on the various types of as-fabricated beryllium, this section is limited to the properties of pressed beryllium: HP, HIP, CIP/S beryllium with either the nuclear grade powder (S-200-F) or the better-performing S-65 powder [11,12]. Plasma-sprayed Be is also described [ 13,14]. •i in where o is the von Mises stress in MPa.…”

Section: Mechanical Propertiesmentioning

confidence: 99%

Status of beryllium development for fusion applications

Billone¹,

Donne²,

Macaulay-Newcombe³

1995

Fusion Engineering and Design

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Beryllium is a leading candidate material for the neutron multiplier of tritium breeding blankets and the plasma facing component of first wall and divertor systems. Depending on the application, the fabrication methods proposed include hot-pressing, hot-isostatic-pressing, cold isostatic pressing/sintering, rotary electrode processing and plasma spraying. Product forms include blocks, tubes, pebbles, tiles and coatings. While, in general, beryllium is not a leading structural material candidate, its mechanical performance, as well its performance with regard to sputtering, heat transport, tritium retention/release, helium-induced swelling and chemical compatibility, is an important consideration in first-wall/blanket design. Differential expansion within the beryllium causes internal stresses which may result in cracking, thereby affecting the heat transport and barrier performance of the material. Overall deformation can result in loading of neighboring structural material. Thus, in assessing the performance of beryllium for fusion applications, it is important to have a good database in all of these performance areas, as well as a set of properties correlations and models for the purpose of interpolation/extrapolation. In this current work, the range of anticipated fusion operating conditions is reviewed. The thermal, mechanical, chemical compatibility, tritium retention/ release, and helium retention/swelling databases are then reviewed for fabrication methods and fusion operating conditions of interest. Properties correlations and uncertainty ranges are also discussed. In the case of the more complex phenomena of tritium retention/release and helium-induced swelling, fundamental mechanisms and models are reviewed in more detail. Areas in which additional data are needed are highlighted, along with some trends which suggest ways of optimizing the performance of beryllium for fusion applications. DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

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Section: Mechanical Propertiesmentioning

confidence: 99%

Status of beryllium development for fusion applications

Billone¹,

Donne²,

Macaulay-Newcombe³

1995

Fusion Engineering and Design

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“…11 extending down below 40 K. The thermal conductivity as a function of temperature for several different sources of beryllium is shown in Figs. II-3-12 13 and II-3-13. 7 The thermal conductivity as a function of temperature of beryllium from six different sources plotted on the same graph is shown in Fig.…”

Section: Ii-3-thermal Propertiesmentioning

confidence: 98%

Atomic, Crystal, Elastic, Thermal, Nuclear, and Other Properties of Beryllium

Goldberg¹

2006

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Section: Mechanical Propertiesmentioning

confidence: 99%

Status of beryllium development for fusion applications

Billone¹

1995

Fusion Engineering and Design

View full text Add to dashboard Cite

Beryllium is a leading candidate material for the neutron multiplier of tritium breeding blankets and the plasma facing component of first wall and divertor systems. Depending on the application, the fabrication methods proposed include hot-pressing, hot-isostatic-pressing, cold isostatic pressing/sintering, rotary electrode processing and plasma spraying. Product forms include blocks, tubes, pebbles, tiles and coatings. While, in general, beryllium is not a leading structural material candidate, its mechanical performance, as well its performance with regard to sputtering, heat transport, tritium retention/release, helium-induced swelling and chemical compatibility, is an important consideration in first-wall/blanket design.Differential expansion within the beryllium causes internal stresses which may result in cracking, thereby affecting the heat transport and barrier performance of the material. Overall deformation can result in loading of neighboring structural material. Thus, in assessing the performance of beryllium for fusion applications, it is important to have a good database in all of these performance areas, as well as a set of properties correlations and models for the purpose of interpolation/extrapolation.In this current work, the range of anticipated fusion operating conditions is reviewed. The thermal, mechanical, chemical compatibility, tritium retention/ release, and helium retention/swelling databases are then reviewed for fabrication methods and fusion operating conditions of interest. Properties correlations and uncertainty ranges are also discussed. In the case of the more complex phenomena of tritium retention/release and helium-induced swelling, fundamental mechanisms and models are reviewed in more detail. Areas in which additional data are needed are highlighted, along with some trends which suggest ways of optimizing the performance of beryllium for fusion applications. DISCLAIMERThis report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

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Properties

Cited by 12 publications

References 20 publications

Status of beryllium development for fusion applications

Status of beryllium development for fusion applications

Atomic, Crystal, Elastic, Thermal, Nuclear, and Other Properties of Beryllium

Status of beryllium development for fusion applications

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