Next European Torus In-Vessel Components

The Next European Torus (NET) in-vessel components consisting of first wall, divertor, and blanket/shield are subject to severe nuclear and thermal radiation. Their reliability and maintainability are crucial to the success of the NET mission. The requirements, options, preliminary design solution, and materials considerations for these components are described.

[1]  W. N. Reynolds,et al.  The nucleation of radiation damage in graphite , 1965 .

[2]  Ronald L. Klueh,et al.  Elevated-temperature tensile properties of irradiated 9 Cr-1 MoVNb steel , 1984 .

[3]  E. Little Fracture mechanics evaluations of neutron irradiated Type 321 austenitic steel , 1986 .

[4]  D. Harries The materials requirements for net , 1987 .

[5]  N. M. Greene,et al.  Radiation-damage calculations: primary knock-on atom spectra, displacement rates, and gas production rates , 1976 .

[6]  R. Klueh,et al.  On the saturation of the DBTT shift of irradiated 12Cr-1MoVW with increasing fluence☆ , 1986 .

[7]  K. Borrass,et al.  Next European Torus Physics Basis , 1988 .

[8]  F. W. Wiffen,et al.  The influence of neutron irradiation at 55°C on the properties of austenitic stainless steels☆ , 1981 .

[9]  M. Baskes,et al.  The retention of deuterium and tritium in POCO AXF‐5Q graphite , 1986 .

[10]  S. Keown,et al.  Effects of heat treatment on structure and properties of 12%Cr steels , 1977 .

[11]  A. A. Haasz,et al.  Flux and energy dependence of methane production from graphite due to H+ impact , 1987 .

[12]  H. R. Higgy,et al.  Effect of fast-neutron irradiation on mechanical properties of stainless steels: AISI types 304, 316 and 347 , 1975 .

[13]  R. Price Thermal conductivity of neutron-irradiated reactor graphites , 1975 .

[14]  D. Kujawski,et al.  An experimental study of uniaxial creep, cyclic creep and relaxation of aisi type 304 stainless steel at room temperature , 1980 .

[15]  R. Klueh,et al.  Helium effects on void formation in 9Cr-1MoVNb and 12Cr-1MoVW irradiated in HFIR☆ , 1986 .

[16]  N. Aldridge,et al.  Radiation hardening in magnox pressure-vessel steels , 1985, Philosophical Transactions of the Royal Society of London. Series A, Mathematical and Physical Sciences.

[17]  K. Dietz,et al.  Wall Protection in JET , 1986 .

[18]  E. E. Bloom Mechanical properties of materials in fusion reactor first-wall and blanket systems , 1979 .

[19]  S. Casadio,et al.  Fabrication of Porous LiAlO2 Ceramic Breeder Material , 1986 .

[20]  H. L. Heinisch,et al.  Spectral effects in low-dose fission and fusion neutron irradiated metals and alloys , 1986 .