[en] Graphite materials have been used in the nuclear fission reactors from the beginning of the reactor development for the speed reduction and reflection of neutron. Graphite materials are used both as a moderator and as a reflector in the core of high temperature gas-cooled reactors, and both as a radiation shielding material and as a reflector in the surrounding of the core for the fast breeder reactor. On the other hand, graphite materials are being positively used as a first wall of plasma as it is known that low Z materials are useful for holding high temperature plasma in the nuclear fusion devices. In this paper the present status of the application of graphite materials to the nuclear fission reactors and fusion devices (reactors) is presented. In addition, a part of results on the related properties to the structural design and safety evaluation and results examined on the subjects that should be done in the future are also described. (author)

No abstract available

[en] Developing plasma-facing and structural materials with Low nuclear Activation (LA), high heat and radiation resistance, is a challenge that the materials community has to address to enable reliable development and safe operation of fusion reactors in the future. This requires scientific innovation, new knowledge, and the exploration of a range of new materials. To address this challenge, the EU fusion programme has set up a Fusion Materials Topical Group to strengthen coordination of long-term fusion materials development for DEMO, and to undertake physically based modelling of radiation induced microstructure and degradation of mechanical properties required to guide the experimental developments. In this paper we describe main radiation effects induced by the intense flux of 14 MeV neutrons in the reference structural materials (i) for Tritium-Breeding Blanket (TBB) modules, LA Ferritic/Martensitic Steel EUROFER, Oxide Dispersion (ODS) EUROFER and ODS ferritic steels, and, (ii) for the divertor, W and W-alloys. Specific issues concerning the peculiar microstructure induced by the impact of α particles on the surface of tungsten, foreseen as a reference protection material, will also be discussed. Modelling radiation effects in EUROFER under fusion reactor relevant conditions is the first priority for the programme, in order to inter-correlate the data obtained with various neutron spectra, contribute to the definition of the irradiation matrix in the future intense source of 14 MeV neutrons, IFMIF, and bring comprehensive understanding and extrapolation capabilities towards the very large range of DEMO operating conditions. Formulating and developing predictive modelling tools is therefore a task of prime significance. Particular care has been taken (i) to focus the modelling effort on the scale where physics can be mastered, i.e. on the scale of the chemical bond, which is triggered by electronic correlation in the case of Fe-Cr system and body cubic centred steels, and, (ii) to validate model prediction at the relevant scale and on the adequate system. The paper will present modelling results based on ab-initio calculation and the development of kinetic tools describing (i) phase stability of Fe-Cr alloy system taking magnetic effects explicitly into account, (ii) point defects energetics in transition metals and their recovery in α-Fe (iii) He and dpa accumulation, and (iv) dynamical properties of dislocations in α-Fe at low and high temperatures. Based on the successful progress of the currently on-going research programme, the Strategic Objectives defined for the next period 2010-2015 (http://www.efda.org/eu_fusion_programme/scientific_and_technical_publications.htm) will be presented and briefly discussed. (author)

[en] The Physics Section supports the IAEA Member States regarding utilization of: Accelerators; Research reactors; Cross-cutting material research; Controlled fusion. The activities in the field of material science include studies of present NPP structural materials; investigation of degradation mechanisms and contribution to research programs of new materials, as well as education and training activities. The Section is participating in the coordinated research projects 'Accelerator Simulation and Theoretical Modeling of Radiation Effects' (Jointly NA-NE) and 'Benchmarking of advanced materials pre-selected for innovative nuclear reactors' (Jointly NA and NE)

[en] This publication is the collection of the papers presented at the title conference. The 76 of the presented papers are indexed individually. (J.P.N.)

[en] Separate abstracts were prepared for 13 of the papers in this volume. The remaining 99 papers dealing with materials in general, were considered outside the subject scope of INIS. (J.P.N.)

[en] In this paper the fusion-fission reactor concept is briefly reviewed. The potential operating modes for fusion-fission systems are reviewed with emphasis on their materials environments, and the materials implications of the assumed mainline fuel producing hybrid are discussed from the reactor designer's point of view. The impact of materials performance on hybrid reactor design is assessed and it is suggested that although materials performance is of vital concern and further materials evaluation work is needed, the materials requirements of the hybrid are an overlap of fusion and fission requirements and appear to be less demanding than those of fission and fusion systems alone. (orig.)

No abstract available

[en] A review is presented of the various applications of ceramic materials in reactors (both fission and fusion) and other nuclear fields, including radioactive waste disposal. Emphasis is on applications in fission reactors: fuel, control elements, moderators, reflectors, shielding. (35 references) (U.S.)

[en] A 174-neutron-group activation cross-section library for 233 ground-state target isotopes and 22 isomeric target isotopes is described. The library, ORACT, was derived from the ACTL Evaluated Neutron Activation Cross-Section Library and was developed for use with existing computer codes that calculate induced activation by convoluting the cross-section data with neutron scalar flux distributions. The activation cross sections extend over the energy range from thermal to MeV and are useful for fusion and fission reactor nuclear design studies as well as other applications