[en] The study deals with the microstructure, the chemical and phase composition and the relative atomic concentration of D/C + Be on the surfaces of carbon fiber composite and beryllium targets simultaneously irradiated by a flux of high-power pulsed deuterium plasma in experiments simulating plasma disruptions . (author)

[en] Prognosis of beryllium aerosols concentration concerns two main aspects: 1 Estimation of emission intensity. 2 Assessment of ventilation efficiency. The first one is a matter of numerous reports been prepared in a framework of ITER EDA (Engineering Design Activity). The second aspect is essential inasmuch as forming concentration of beryllium aerosols depends on ventilation efficiency vitally. The main mechanisms of airborne beryllium contaminations are as follows: Sublimation and bulk condensation. Erosion and mechanical disintegration. Responding from contaminated surfaces (secondary pollution). Our report at BeWS-3 contains some theoretical and experimental data concerning above-mentioned mechanisms. Herewith, an attempt of enhancement of enhancement and generalization of known and new results is presented. (author)

[en] The behavior of the plasma facing Be-elements in the International Thermonuclear Experimental Reactor ITER will be affected by the re-deposition of other eroded plasma facing materials. The effect of carbon- and tungsten-additions on the microstructure, chemical composition and hydrogen isotope accumulation in the sputtered and re-deposited layers of beryllium TGP-56 at its interaction with 200 - 300 eV hydrogen isotope ions was studied in the MAGRAS facility equipped with a magnetron sputtering system. (author)

[en] This paper presents the fabric ability development for the ITER first wall through the fabrication of a real size first wall panel mock-up without beryllium armor and a partial mock-up of the first wall panel with beryllium armor. Microscopic observation and mechanical test of the hot isostatic pressed Be/Cu-alloy joints were also performed of which results showed good bond ability of the joints. Finally the fabrication procedure of the ITER first wall panel has been established. (author)

[en] The study analyzes the possibilities of utilization beryllium ingots produced at UMZ (Ulba Metallurgical Plant) for the purpose of ITER program. The results of comparative analysis of specification requirement to S-65 grade chemical compound and statistics data of UMZ beryllium ingots impurities content are presented. It has been demonstrated that beryllium industrial ingots produced at UMZ can be used for a production of powders and billets conforming the requirements of ITER specification. Beryllium ingots production flow chart, description of basic process equipment, the layout of metallurgical production upgrade, the results of such upgrade implementation are complimentary data to this study. The study illustrated with explanatory drawings. (author)

[en] Thermal desorption of deuterium from its ion irradiated Be₁₂Ti and microstructural change during irradiation were examined to understand deuterium retention and desorption property. Total retention of deuterium in Be₁₂Ti is much smaller than that of beryllium at the wide temperature range. For implantation of 2 x 10²¹D/m² at room temperature, 10% of implanted deuterium is retained and most of them are desorbed around 400K, where a high-density of cavities were formed. For the case of beryllium, 83% of implanted deuterium is retained. These results indicate that deuterium trapping efficiency of cavity in the Be₁₂Ti is much lower than that of beryllium. (author)

[en] The report presents results of surveillance of 1836 workers of beryllium production of Ulba Metallurgical Plant JSC with the acute and chronic forms of occupation diseases for 52 years of its operation. The dependence of acute and chronic occupation lesions on the protection degree is shown. It has been found out that, the risk of getting an occupation disease increases sharply at the moments of experimental works and at the time of reconstruction and some other extreme conditions in the production, that is supported by fixed lesions of eye mucous coat, skin and lung lesions. In this case, the readiness of people for their work in deleterious conditions and their personal responsibility for following the regulations of safety occupational standards plays a definite role. Therefore, the issues of protection are of paramount importance in prophylaxis both of acute and chronic exposure to beryllium. An influence of duration of service and occupation on chronic beryllium diseases is shown. A parallel between the lung beryllium disease and skin lesions by insoluble beryllium compounds is drawn for the first time. (author)

[en] This paper presents an overview of Flibe (2Lif·BeF₂) molten salt research activities conducted at the INEEL as part of the Japan-US JUPITER-II joint research program. The research focuses on tritium/chemistry issues for self-cooled Flibe tritium breeder applications and includes the following activities: (1) Flibe preparation, purification, characterization and handling, (2) development and testing of REDOX strategies for containment material corrosion control, (3) tritium behavior and management in Flibe breeder systems, and (4) safety testing (e.g., mobilization of Flibe during accident scenarios). This paper describes the laboratory systems developed to support these research activities and summarizes key results of this work to date. (author)

[en] Experiment of deuterium permeation through Ni facing with purified Flibe is being carried out under the Japan-US joint research project (JUPITER-II). The experiment has been proceeding in the following phases; (i) fabrication and assembly of a dual-probe permeation apparatus, (ii) a single-probe Ni/D₂, permeation experiment without Flibe, (iii) a dual-probe Ar/Ni/D₂ permeation experiment without Flibe, (iv) Flibe chemical purification by HF/H₂ gas bubbling, (v) physical purification by Flibe transport through a porous Ni filter, (vi) Ar/Ni/Flibe/Ni/D₂ permeation experiment using the dual Ni probe, and (vii) Ar/Ni/Flibe/Ni/HT permeation experiment. The present paper describe results until the Ar/Ni/Flibe/Ni/D₂ permeation experiment in detail. (author)

[en] Impurities in beryllium for fusion blanket application such as armor of the first wall and neutron multiplier is one of important issues to perform its properties. In this study, tritium production rate evaluation was carried out on the base of JMTR irradiation test that simulated the breeding blanket and the impact of impurity on tritium production rate was discussed. Influence of impurities in S200F beryllium was therefore less than 1%, concerning tritium production rate. Accordingly, it is reasonable to estimate extremely small impact on tritium production rate in case of fusion application that uses high purity beryllium such as S65C. (author)