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168 results on '"Arbeiter, F."'

2. The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European Japanese project towards a Li(d,xn) fusion relevant neutron source

Author

Knaster, J., Ibarra, A., Abal, J., Sena, A. Abou, Arbeiter, F., Arranz, F., Arroyo, J. M., Bargallo, E., Beauvais, P. Y., Bernardi, D., Casal, N., Carmona, J. M., Chauvin, N., Comunian, M., Delferriere, O., Delgado, A., Arocas, P. Diaz, Fischer, U., Frisoni, M., Garcia, A., Garin, P., Gobin, R., Gouat, P., Groesche, F., Heidinger, R., Ida, M., Kondo, K., Kikuchi, T., Kubo, T., Tonqueze, Y. Le, Leysen, W., Mas, A., Massaut, V., Matsumoto, H., Micciche, G., Mittwollen, M., Mora, J. C., Mota, F., Nghiem, P. A. P., Nitti, F., Nishiyama1, K., Ogando, F., hira, S. O, Oliver, C., Orsini, F., Perez, D., Perez, M., Pinna, T., Pisent, A., Podadera, I., Porfiri, M., Pruneri, G., Quera, V., Rapisarda, D., Roman, R., Shingala, M., Soldaini, M., Sugimoto, M., Theile, J., Tian, K., Umeno, H., Uriot, D., Wakai, E., Watanabe, K., Weber, M., Yamamoto, M., and Yokomine, T.

Subjects
Physics - Accelerator Physics
Abstract

The International Fusion Materials Irradiation Facility (IFMIF), presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase under the frame of the Broader Approach Agreement between Europe and Japan, accomplished in summer 2013, on schedule, its EDA phase with the release of the engineering design report of the IFMIF plant, which is here described. Many improvements of the design from former phases are implemented, particularly a reduction of beam losses and operational costs thanks to the superconducting accelerator concept, the re-location of the quench tank outside the test cell (TC) with a reduction of tritium inventory and a simplification on its replacement in case of failure, the separation of the irradiation modules from the shielding block gaining irradiation flexibility and enhancement of the remote handling equipment reliability and cost reduction, and the water cooling of the liner and biological shielding of the TC, enhancing the efficiency and economy of the related sub-systems. In addition, the maintenance strategy has been modified to allow a shorter yearly stop of the irradiation operations and a more careful management of the irradiated samples. The design of the IFMIF plant is intimately linked with the EVA phase carried out since the entry into force of IFMIF/EVEDA in June 2007.

Published
2021
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3. TRL analysis of IFMIF-DONES

Author

Brañas, B., Maestre, J., Bernardi, D., Ibarra, A., Arbeiter, F., Arena, P., Arranz, F., Becerril, S., Cappelli, M., Chel, S., Castellanos, J., Favuzza, P., Jiménez-Rey, D., Krolas, W., Martin-Fuertes, F., Micciché, G., Nitti, F.S., Podadera, I., Qiu, Y., Regidor, D., Renard, B., Tadic, T., Varela, R., and Weber, M.

Published
2024
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4. Overview of recent advancements in IFMIF-DONES neutronics activities

Author

Qiu, Y., Ansorge, M., Álvarez, I., Ambrožič, K., Berry, T., Bieńkowska, B., Chohan, H., Čufar, A., Dworak, D., Dezsi, T., Eade, T., García, J., Jimenez-Rey, D., Lengar, I., Lopez-Revelles, A.J., Lopez, V., Mendoza, E., Mota, F., Martinez-Echevarria, M.J., Ogando, F., Park, J., Piotrowski, T., Serikov, A., Stankunas, G., Tidikas, A., Tracz, G., Žerovnik, G., Arbeiter, F., Arranz, F., Becerril, S., Cara, P., Bernardi, D., Castellanos, J., Gutiérrez, J., Ibarra, A., Królas, W., Maestre, J., Martín-Fuertes, F., Marugán, J.C., Micciché, G., Martínez-Serrano, J., Nitti, F.S., Podadera, I., Wiącek, U., and Fischer, U.

Published
2024
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6. Overview of IFMIF-DONES diagnostics: Requirements and techniques

Author

Torregrosa-Martin, C., Ibarra, A., Aguilar, J., Ambi, F., Arranz, F., Arbeiter, F., Bagnasco, A., Becerril, S., Bernardi, D., Bolzon, B., Botta, E., Brenneis, B., Cappelli, M., Cara, P., Castellanos, J., Cosic, D., De la Morena, C., Diez, A., Ericsson, G., García, A., García, M., Garcinuño, B., Gutiérrez, J., Gutiérrez, V., Jimenez-Rey, D., Dezsi, T., Ferreira, M. Juni, Fiore, S., Krolas, W., Lorenzo, R., Luque, M., Maciá, L., Marroncle, J., Martin-Fuertes, F., Marugán, J.C., Maestre, J., Meléndez, C., Miccichè, G., Mollá, J., Moreno, A., Nitti, F.S., Núñez, C., Ogando, F., Pinna, T., Oliver, C., Podadera, I., Prieto, C., Prokopowicz, R., Qiu, Y., Rapisarda, D., Regidor, D., Rodríguez, E., Sabogal, A., Sánchez-Herranz, D., Sanmarti, M., Seguí, L., Serikov, A., Tadić, T., Talarowska, A., Wiacek, U., Weber, M., Valenzuela, J., and Zsakai, A.

Published
2023
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14. Fracture Mechanics Methods to Assess the Lifetime of Thermoplastic Pipes

Author

Arbeiter, F., Pinter, G., Lang, R. W., Frank, A., Hull, Robert, Series editor, Jagadish, Chennupati, Series editor, Kawazoe, Yoshiyuki, Series editor, Osgood, Richard M., Series editor, Parisi, Jürgen, Series editor, Seong, Tae-Yeon, Series editor, Uchida, Shin-ichi, Series editor, Wang, Zhiming M., Series editor, Grellmann, Wolfgang, editor, and Langer, Beate, editor

Published
2017
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23. Initial DEMO tokamak design configuration studies

Author

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., and Wenninger, R.

Published
2015
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25. Numerical Solution Strategies in Permeation Processes

Author

Weth, Axel von der, Piccioni Koch, D., Arbeiter, F., Klimenko, D., Schlindwein, G., Schulz, M. J., Pasler, M. J.., Prothmann, N., and Zinn, K.

Subjects
Technology, Radiation, General Materials Science, Condensed Matter Physics, ddc:600
Abstract

In this work, the strategy for numerical solutions in transport processes is investigated. Permeation problems can be solved analytically or numerically by means of the Finite Difference Method (FDM), while choosing the Euler forward explicit or Euler backwards implicit formalism. The first method is the easiest and most commonly used, while the Euler backwards implicit is not yet well established and needs further development. Hereafter, a possible solution of the Crank-Nicolson algorithm is presented, which makes use of matrix multiplication and inversion, instead of the step-by-step FDM formalism. If one considers the one-dimensional diffusion case, the concentration of the elements can be expressed as a time dependent vector, which also contains the boundary conditions. The numerically stable matrix inversion is performed by the Branch and Bound (B&B) algorithm [2]. Furthermore, the paper will investigate, whether a larger time step can be used for speeding up the simulations. The stability range is investigated by eigenvalue estimation of the Euler forward and Euler backward. In addition, a third solver is considered, referred to as Combined Solver, that is made up of the last two ones. Finally, the Crank-Nicolson solver [9] is investigated. All these results are compared with the analytical solution. The solver stability is analyzed by means of the Steady State Eigenvector (SSEV), a mathematical entity which was developed ad hoc in the present work. In addition, the obtained results will be compared with the analytical solution by Daynes [6,7].

Published
2021
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35. The IFMIF-DONES fusion oriented neutron source: evolution of the design

Author

Królas, W., primary, Ibarra, A., additional, Arbeiter, F., additional, Arranz, F., additional, Bernardi, D., additional, Cappelli, M., additional, Castellanos, J., additional, Dézsi, T., additional, Dzitko, H., additional, Favuzza, P., additional, García, A., additional, Gutiérrez, J., additional, Lewitowicz, M., additional, Maj, A., additional, Martin-Fuertes, F., additional, Micciché, G., additional, Muñoz, A., additional, Nitti, F.S., additional, Pinna, T., additional, Podadera, I., additional, Pons, J., additional, Qiu, Y., additional, Román, R., additional, Toth, M., additional, and Zsakai, A., additional

Published
2021
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39. New approach to the conceptual design of STUMM: A module dedicated to the monitoring of neutron and gamma radiation fields generated in IFMIF-DONES

Author

Wi��cek, U., Arbeiter, F., Bie��kowska, B., Bocian, D., Castellanos, J., Igielski, A., Kotu��a, J., Kr��las, W., Kurowski, A., Madejowski, G., Prokopowicz, R., Ortwein, R., and ��wierblewski, J.

Subjects
Technology, ddc:600
Abstract

International Fusion Materials Irradiation Facility ��� DEMOsingle bondOriented Neutron Source (IFMIF-DONES) is a planned powerful neutron source, which will generate an intense flux of neutrons (up to ���1015n/s/cm2) with a fusion-relevant energy spectrum. It will be an accelerator source based on deuteron beam - lithium target reactions. The engineering design of IFMIF-DONES is elaborated in the frame of the Early Neutron Source work package of the EUROfusion consortium. The facility will be dedicated to the irradiation of suitable structural materials planned for the construction of future fusion reactors such as DEMO (Demonstration Fusion Power Plant). Start-up Monitoring Module (STUMM) is designed to monitor radiation and thermal conditions during the commissioning phase of IFMIF-DONES, characterize the produced neutron flux and validate neutronic modeling of the facility. The conceptual design of STUMM is prepared by a team of physicists and engineers from the Institute of Nuclear Physics Polish Academy of Sciences (IFJ PAN) and the National Centre for Nuclear Research (NCBJ), Poland. This paper presents the concept of STUMM, the proposed design of the module, and selected measuring systems.

Published
2021

43. IFMIF, the European-Japanese efforts under the Broader Approach Agreement towards a Li(d,xn) neutron source:current status and future options

Author

Knaster, J., Arbeiter, F., Cara, P., Heidinger, R., Ibarra, A., Kasugai, A., Kondo, H., Micciche, G., Ochiai, K., S., O’hira, Okumura, Y., Sakamoto, K., and Wakai, E.

Abstract

The necessity of a neutron source for fusion materials research was identified already in the 70s. Though neutrons induced degradation present similarities on a mechanistic approach, thresholds energies for cru- cial transmutations are typically above fission neutrons spectrum. The generation of He via 56 Fe (n, α) 53 Cr in future fusion reactors with around 12 appm/dpa will lead to swelling and structural materials embrittlement. Existing neutron sources, namely fission reactors or spallation sources lead to different degradation, attempts for extrapolation are unsuccessful given the absence of experimental observations in the operational ranges of a fusion reactor. Neutrons with a broad peak at 14 MeV can be generated with Li(d,xn) reactions; the technological effort s that started with FMIT in the early 80s have finally ma- tured with the success of IFMIF/EVEDA under the Broader Approach Agreement. The status today of five technological challenges, perceived in the past as most critical, are addressed. These are: 1. the feasibil- ity of IFMIF accelerators, 2. the long term stability of lithium flow at IFMIF nominal conditions, 3. the potential instabilities in the lithium screen induced by the 2 ×5 MW impacting deuteron beam, 4. the uniformity of temperature in the specimens during irradiation, and 5. the validity of data provided with small specimens. Other ideas for fusion material testing have been considered, but they possibly are ei- ther not technologically feasible if fixed targets are considered or would require the results of a Li(d,xn) facility to be reliably designed. In addition, today we know beyond reasonable doubt that the cost of IFMIF, consistently estimated throughout decades, is marginal compared with the cost of a fusion reactor. The less ambitious DEMO reactor performance being considered correlates with a lower need of fusion neutrons flux; thus IFMIF with its two accelerators is possibly not needed since with only one acceler- ator as the European DONES or the Japanese A-FNS propose, the present needs > 10 dpa/fpy would be fulfilled. World fusion roadmaps stipulate a fusion relevant neutron source by the middle of next decade, the success of IFMIF/EVEDA phase is materializing this four decades old dream.

Published
2016

46. Fatigue crack propagation in a component produced by additive manufacturing of polymer materials

Author

Trávníček, L., Arbeiter, F., Dlhý, P., Spoerk, M., Náhlík, L., Hutař, P., Adámek, Vítězslav, Jonášová, Alena, Plánička, Stanislav, and Zajíček, Martin

Subjects
polymerní materiály, polymer materials, experiment, kyselina polymléčná, numerical modelling, fatigue, numerické modelování, únava, polylactic acid, additive manufacturing, aditivní výroba
Abstract

project m- IPMinfra (CZ.02.1.01/0.0/0.0/16_013/0001823)

Published
2019

48. Lifetime estimation of polyoxymethelene under mixed-mode loading conditions

Author

Slávik, O., Hutař, P., Gosch, A., Berer, M., Vojtek, T., Arbeiter, F., Pinter, G., Náhlík, L., Adámek, Vítězslav, Jonášová, Alena, Plánička, Stanislav, and Zajíček, Martin

Subjects
numerical simulations, numerické simulace, odhad životnosti, polyoxymethylen, lifetime estimation, polyoxymethelene
Abstract

project m-IPMinfra (CZ.02.1.01/0.0/0.0/16_013/0001823) and the equipment and the base of research infrastructure IPMinfra were used during the research activities. Also, thanks are due to the specific research project FSI-S-17-4386 of the Faculty of Mechanical Engineering, BUT.

Published
2019

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