Materials for DEMO and reactor applications-boundary conditions and new concepts

被引：115

作者：

Coenen, J. W. ^{[1
]}

Antusch, S. ^{[2
]}

Aumann, M. ^{[1
]}

Biel, W. ^{[1
,3
]}

Du, J. ^{[1
]}

Engels, J. ^{[1
]}

Heuer, S. ^{[1
]}

Houben, A. ^{[1
]}

Hoeschen, T. ^{[4
]}

Jasper, B. ^{[1
]}

Koch, F. ^{[4
]}

Linke, J. ^{[1
]}

Litnovsky, A. ^{[1
]}

Mao, Y. ^{[1
]}

Neu, R. ^{[4
,5
]}

Pintsuk, G. ^{[1
]}

Riesch, J. ^{[4
]}

Rasinski, M. ^{[1
]}

Reiser, J. ^{[2
]}

Rieth, M. ^{[2
]}

Terra, A. ^{[1
]}

Unterberg, B. ^{[1
]}

Weber, Th ^{[1
]}

Wegener, T. ^{[1
]}

You, J-H ^{[4
]}

Linsmeier, Ch ^{[1
]}

机构：

[1] Forschungszentrum Julich, Inst Energie & Klimaforsch, Julich, Germany

[2] Karlsruhe Inst Technol, Inst Appl Mat, Eggenstein Leopoldshafen, Germany

[3] Univ Ghent, Dept Appl Phys, Ghent, Belgium

[4] Max Planck Inst Plasma Phys, Garching, Germany

[5] Tech Univ Munich, Boltzmannstr 15, D-85748 Garching, Germany

来源：

PHYSICA SCRIPTA | 2016年 / T167卷

关键词：

PWI; materials; divertor; neutrons; DEMO; HIGH-HEAT-FLUX; PLASMA-FACING MATERIALS; FUSION POWER-PLANT; TUNGSTEN; EUROFER; MICROSTRUCTURE; COMPOSITES; PERMEATION; DESIGN;

D O I：

10.1088/0031-8949/2015/T167/014002

中图分类号：

O4 [物理学];

学科分类号：

0702 ;

摘要：

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 W-f/W 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.

引用

页数：11

共 56 条

[1] Manufacturing and joining technologies for helium cooled divertors [J].

Aktaa, J. ;

Basuki, W. W. ;

Weber, T. ;

Norajitra, P. ;

Krauss, W. ;

Konys, J. .

FUSION ENGINEERING AND DESIGN, 2014, 89 (7-8) :913-920

[2]

[Anonymous], 2009, HDB ACTIVATION DATA

[3] Mechanical and microstructural investigations of tungsten and doped tungsten materials produced via powder injection molding [J].

Antusch, Steffen ;

Armstrong, David E. J. ;

Ben Britton, T. ;

Commin, Lorelei ;

Gibson, James S. K. -L. ;

Greuner, Henri ;

Hoffmann, Jan ;

Knabl, Wolfram ;

Pintsuk, Gerald ;

Rieth, Michael ;

Roberts, Steve G. ;

Weingaertner, Tobias .

NUCLEAR MATERIALS AND ENERGY, 2015, 3-4 :22-31

[4] A new fully automatic PIM tool to replicate two component tungsten DEMO divertor parts [J].

Antusch, Steffen ;

Commin, Lorelei ;

Heneka, Jochen ;

Piotter, Volker ;

Plewa, Klaus ;

Walter, Heinz .

FUSION ENGINEERING AND DESIGN, 2013, 88 (9-10) :2461-2465

[5] Initial DEMO tokamak design configuration studies [J].

Bachmann, Christian ;

Aiello, G. ;

Albanese, R. ;

Ambrosino, R. ;

Arbeiter, F. ;

Aubert, J. ;

Boccaccini, L. ;

Carloni, D. ;

Federici, G. ;

Fischer, U. ;

Kovari, M. ;

Li Puma, A. ;

Loving, A. ;

Maione, I. ;

Mattei, M. ;

Mazzone, G. ;

Meszaros, B. ;

Palermo, I. ;

Pereslavtsev, P. ;

Riccardo, V. ;

Sardain, P. ;

Taylor, N. ;

Villari, S. ;

Vizvary, Z. ;

Vaccaro, A. ;

Visca, E. ;

Wenninger, R. .

FUSION ENGINEERING AND DESIGN, 2015, 98-99 :1423-1426

[6]

Biel W, 2015, COMMUNICATION

[7] Plasma facing and high heat flux materials - needs for ITER and beyond [J].

Bolt, H ;

Barabash, V ;

Federici, G ;

Linke, J ;

Loarte, A ;

Roth, J ;

Sato, K .

JOURNAL OF NUCLEAR MATERIALS, 2002, 307 :43-52

[8]

Boutard P., 2012, EFDA125272

[9] Fuel retention studies with the ITER-Like Wall in JET [J].

Brezinsek, S. ;

Loarer, T. ;

Philipps, V. ;

Esser, H. G. ;

Gruenhagen, S. ;

Smith, R. ;

Felton, R. ;

Banks, J. ;

Belo, P. ;

Boboc, A. ;

Bucalossi, J. ;

Clever, M. ;

Coenen, J. W. ;

Coffey, I. ;

Devaux, S. ;

Douai, D. ;

Freisinger, M. ;

Frigione, D. ;

Groth, M. ;

Huber, A. ;

Hobirk, J. ;

Jachmich, S. ;

Knipe, S. ;

Krieger, K. ;

Kruezi, U. ;

Marsen, S. ;

Matthews, G. F. ;

Meigs, A. G. ;

Nave, F. ;

Nunes, I. ;

Neu, R. ;

Roth, J. ;

Stamp, M. F. ;

Vartanian, S. ;

Samm, U. .

NUCLEAR FUSION, 2013, 53 (08)

[10]

Causey RA, 2012, COMPREHENSIVE NUCLEAR MATERIALS, VOL 4: RADIATION EFFECTS IN STRUCTURAL AND FUNCTIONAL MATERIALS FOR FISSION AND FUSION REACTORS, P511

← 1 2 3 4 5 6 →