B. Jasper
Forschungszentrum Jülich
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Featured researches published by B. Jasper.
Physica Scripta | 2016
J. Riesch; Y. Han; J. Almanstötter; J. W. Coenen; T. Höschen; B. Jasper; P. Zhao; Ch. Linsmeier; R. Neu
For the next step fusion reactor the use of tungsten is inevitable to suppress erosion and allow operation at elevated temperature and high heat loads. Tungsten fibre-reinforced composites overcome the intrinsic brittleness of tungsten and its susceptibility to operation embrittlement and thus allow its use as a structural as well as an armour material. That this concept works in principle has been shown in recent years. In this contribution we present a development approach towards its use in a future fusion reactor. A multilayer approach is needed addressing all composite constituents and manufacturing steps. A huge potential lies in the optimization of the tungsten wire used as fibre. We discuss this aspect and present studies on potassium doped tungsten wire in detail. This wire, utilized in the illumination industry, could be a replacement for the so far used pure tungsten wire due to its superior high temperature properties. In tensile tests the wire showed high strength and ductility up to an annealing temperature of 2200 K. The results show that the use of doped tungsten wire could increase the allowed fabrication temperature and the overall working temperature of the composite itself.
Physica Scripta | 2016
J. W. Coenen; Steffen Antusch; M. Aumann; W. Biel; J. Du; J. Engels; S. Heuer; A. Houben; T. Hoeschen; B. Jasper; F. Koch; J. Linke; A. Litnovsky; Y Mao; R. Neu; G. Pintsuk; J. Riesch; M. Rasinski; Jens Reiser; Michael Rieth; A. Terra; B. Unterberg; Th. Weber; T. Wegener; J.-H. You; Ch. Linsmeier
DEMO is the name for the first stage prototype fusion reactor considered to be the next step after ITER towards realizing fusion. For the realization of fusion energy especially, materials questions pose a significant challenge already today. Heat, particle and neutron loads are a significant problem to material lifetime when extrapolating to DEMO. For many of the issues faced, advanced materials solutions are under discussion or already under development. In particular, components such as the first wall and the divertor of the reactor can benefit from introducing new approaches such as composites or new alloys into the discussion. Cracking, oxidation as well as fuel management are driving issues when deciding for new materials. Here composites as well as strengthened CuCrZr components together with oxidation resilient tungsten alloys allow the step towards a fusion reactor. In addition, neutron induced effects such as transmutation, embrittlement and after-heat and activation are essential. Therefore, when designing a component an approach taking into account all aspects is required.
Materials Science Forum | 2015
B. Jasper; J. W. Coenen; J. Riesch; T. Höschen; Martin Bram; Christian Linsmeier
The composite material tungsten fiber-reinforced tungsten (Wf/W) addresses the brittleness of tungsten by extrinsic toughening through introduction of energy dissipation mechanisms. These mechanisms allow the release of stress peaks and thus improve the materials resistance against crack growth. Wf/W samples produced via chemical vapor infiltration (CVI) indeed show higher toughness in mechanical tests than pure tungsten. By utilizing powder metallurgy (PM) one could benefit from available industrialized approaches for composite production and alloying routes. In this contribution the PM method of hot isostatic pressing (HIP) is used to produce Wf/W samples. A variety of measurements were conducted to verify the operation of the expected toughening mechanisms in HIP Wf/W composites. The interface debonding behavior was investigated in push-out tests. In addition, the mechanical properties of the matrix were investigated, in order to deepen the understanding of the complex interaction between the sample preparation and the resulting mechanical properties of the composite material. First HIP Wf/W single-fiber samples feature a compact matrix with densities of more than 99% of the theoretical density of tungsten. Scanning electron microscopy (SEM) analysis further demonstrates an intact interface with indentations of powder particles at the interface-matrix boundary. First push-out tests indicate that the interface was damaged by HIPing.
Physica Scripta | 2017
Y. Mao; J. W. Coenen; J. Riesch; S. Sistla; J. Almanstötter; B. Jasper; A. Terra; T. Höschen; H. Gietl; Martin Bram; Jesús González-Julián; Ch. Linsmeier; Christoph Broeckmann
In future fusion reactors, tungsten is the prime candidate material for the plasma facing components. Nevertheless, tungsten is prone to develop cracks due to its intrinsic brittleness—a major concern under the extreme conditions of fusion environment. To overcome this drawback, tungsten fiber reinforced tungsten (Wf/W) composites are being developed. These composite materials rely on an extrinsic toughing principle, similar to those in ceramic matrix composite, using internal energy dissipation mechanisms, such as crack bridging and fiber pull-out, during crack propagation. This can help Wf/W to facilitate a pseudo-ductile behavior and allows an elevated damage resilience compared to pure W. For pseudo-ductility mechanisms to occur, the interface between the fiber and matrix is crucial. Recent developments in the area of powder-metallurgical Wf/W are presented. Two consolidation methods are compared. Field assisted sintering technology and hot isostatic pressing are chosen to manufacture the Wf/W composites. Initial mechanical tests and microstructural analyses are performed on the Wf/W composites with a 30% fiber volume fraction. The samples produced by both processes can give pseudo-ductile behavior at room temperature.
Composite Interfaces | 2018
Stephan Schönen; B. Jasper; J. W. Coenen; Juan Du; T. Höschen; J. Riesch; Ghaleb Natour; R. Neu; Christian Linsmeier
ABSTRACT To overcome the intrinsic brittleness of tungsten (W), a tungsten fiber-reinforced tungsten-composite material (Wf/W) is a possible solution. The introduction of energy dissipation mechanisms like fiber bridging or fiber pull-out by means of an engineered interface between fiber and matrix mitigate the brittleness of tungsten and lead to a pseudo-ductile material behaviour. The push-out test of single-fiber samples is an experimental method to investigate the properties of the interface between fiber and matrix of composite materials. It is widely used for the investigation of ceramic composites. This method was also used to investigate the debonding and frictional properties of the Er2O3 interface region between fiber and matrix of Wf/W single-fiber samples made by CVDand HIP-processes. In this article finite element calculations are used to get a better understanding of the processes acting in the interface during a push-out test of Wf/W. A detailed overview of the debonding progress and of the corresponding stress states of the interface during the different stages of the test is presented. In addition the sensitivity of the push-out behaviour regarding the different interface properties and the plastic flow curve of the tungsten fiber are investigated. Graphical Abstract
Fusion Engineering and Design | 2017
J. W. Coenen; Y. Mao; J. Almanstötter; A. Calvo; S. Sistla; H. Gietl; B. Jasper; J. Riesch; Michael Rieth; G. Pintsuk; F. Klein; A. Litnovsky; A.V. Mueller; T. Wegener; J.-H. You; Ch. Broeckmann; C. García-Rosales; R. Neu; Ch. Linsmeier
Nuclear materials and energy | 2016
B. Jasper; S. Schoenen; Juan Du; T. Hoeschen; F. Koch; Christian Linsmeier; R. Neu; J. Riesch; A. Terra; J. W. Coenen
Composites Part A-applied Science and Manufacturing | 2018
Y. Mao; J. W. Coenen; J. Riesch; S. Sistla; J. Almanstötter; B. Jasper; A. Terra; T. Höschen; H. Gietl; Ch. Linsmeier; Christoph Broeckmann
symposium on fusion technology | 2016
J. W. Coenen; J. Riesch; J.-H. You; M. Riethm; G. Pintsuk; H. Gietl; B. Jasper; F. Klein; A. Litnovsky; Y. Mao; A. von Müller; S. Sistla; T. Wegener; Christoph Broeckmann; Ch. Linsmeier; R. Neu
17th Int. Conference on Fusion Reactor Materials (ICFRM-17) | 2015
J. W. Coenen; J. Riesch; T. Hoeschen; Ch. Linsmeier; R. Neu; S. Schoenen; J. Du; B. Jasper