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Assessment of creep in reactor-irradiated CuCrZr alloy intended for the ITER first wall panels

Autor: R.W. Bosch, Andrei Gusarov, F. Zacchia, Christoph Pohl, Heikkinen Samuli, Steven Van Dyck, V.R. Barabash, R. Eaton, Torsten Pfalz

Publikováno v: Fusion Engineering and Design. 137:112-123

CuCrZr alloy is candidate heat sink material for the ITER blanket, first wall, and divertor. During ITER operation it will be exposed to a combination of elevated temperatures, heat flux, and intense fast neutron radiation. This environment will chal

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::ce439766154970d7f053dadb49dca066
https://doi.org/10.1016/j.fusengdes.2018.09.001

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EU contribution to the procurement of the ITER blanket first wall

Autor: D Conchon, Marcos Pérez, Patrice Nogué, P. Lorenzetto, P. Sherlock, Leticia Ruiz Gutierrez, Paul Marshall, B. Bellin, Stephen Hardaker, Fernando Samaniego, F. Zacchia, Bruno Boireau, Tindaro Cicero, P. Bucci, Georges Dellopoulos, Stefano Banetta

Publikováno v: Fusion Engineering and Design. :661-665

Fusion for Energy (F4E), the European Union’s Domestic Agency for ITER, is responsible for the procurement of about 50% of the ITER blanket first wall (FW), called normal heat flux FW. A procurement strategy has been implemented by the In-Vessel Pr

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::4483626e5623410932a9495630d5c7b1
https://doi.org/10.1016/j.fusengdes.2016.02.024

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An investigation of pulsed phase thermography for detection of disbonds in HIP-bonded beryllium tiles in ITER normal heat flux first wall (NHF FW) components

Autor: Paul Mummery, J. Bushell, P. Sherlock, B. Bellin, F. Zacchia

Publikováno v: Fusion Engineering and Design. :1244-1249

Pulsed phase thermography (PPT) is a non destructive examination (NDE) technique, traditionally used in the Aerospace Industry for inspection of composite structures, which combines characteristics and benefits of flash thermography and lock-in therm

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5f2076f015521d46e92d3d45e592fd48
https://doi.org/10.1016/j.fusengdes.2015.01.030

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In-pile testing of ITER first wall mock-ups at relevant thermal loading conditions in the LVR-15 nuclear research reactor

Autor: Rudolf Vsolak, Tomas Klabik, Ondrej Zlamal, B. Bellin, Jan Kysela, Slavomir Entler, F. Zacchia

Publikováno v: Fusion Engineering and Design. :1271-1275

The TW3 in-pile rig enabled the thermal fatigue testing of ITER primary first wall mock-ups in the core of the nuclear reactor. This experiment investigated the neutron irradiation influence on the design performance under high heat flux testing. A t

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::ed865de63bdd1c0db6a1579229e2438f
https://doi.org/10.1016/j.fusengdes.2015.01.040

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Progress in the design of Normal Heat Flux First Wall panels for ITER

Autor: Gabriele D’Amico, Sabas Cardenes, B. Bellin, Tindaro Cicero, Barbara Calcagno, Elena Alvaro, Jordi Ayneto Pou, Marc Jimenez, R. Raffray, S. Gicquel, F. Zacchia, Georges Dellopoulos, P. Chappuis, Stefano Banetta, R. Mitteau

Publikováno v: Fusion Engineering and Design. :1256-1262

A typical NHF FW panel consists of a series of fingers, which represent the elementary plasma facing units and are designed to withstand 15,000 cycles at 2 MW/m 2 . The fingers are mechanically joined and supported by a back structural element or “

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::f8001dc4955753bd6f9d724fd46562f7
https://doi.org/10.1016/j.fusengdes.2015.01.023

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Manufacturing and testing of a ITER First Wall Semi-Prototype for EUDA pre-qualification

Autor: P. Lorenzetto, I. Bobin, F. Zacchia, P. Nogue, R. Eaton, R. Raffray, R. Mitteau, A. Cottin, Andreas Bürger, Juan Du, Jochen Linke, P. Boiffard, Stefano Banetta, B. Boireau, B. Bellin, Th. Weber, Gerald Pintsuk

Publikováno v: Fusion Engineering and Design. :1211-1215

This paper describes the main activities carried out in the frame of EU-DA prequalification for the supply of Normal Heat Flux (NHF) First Wall (FW) panels to ITER. A key part of these activities is the manufacturing development, the fabrication and

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::4b672bb0cca5b5551a8795d0dc409557
https://doi.org/10.1016/j.fusengdes.2015.01.016

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Manufacturing of small-scale mock-ups and of a semi-prototype of the ITER Normal Heat Flux First Wall

Autor: F. Zacchia, B. Boireau, I. Bobin-Vastra, R. Mitteau, Stefano Banetta, P. Lorenzetto, A. Cottin, R. Raffray, R. Eaton

Publikováno v: Fusion Engineering and Design. 89:970-974

This paper describes the manufacturing development and fabrication of reduced scale ITER First Wall (FW) mock-ups of the Normal Heat Flux (NHF) design, including a “semi-prototype” with a dimension of 305 mm × 660 mm, corresponding to about 1/6

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::3767f8e0503a0a195863fb14345a9475
https://doi.org/10.1016/j.fusengdes.2014.04.020

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Design evolution and integration of the ITER in-vessel components

Publikováno v: Fusion Engineering and Design. 88:1955-1959

The ITER in-vessel components have experienced a major redesign since the ITER Design Review of 2007. A set of in-vessel vertical stabilization (VS) coils and a set of in-vessel Edge Localized Mode (ELM) control coils have been implemented. The blank

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::416cd3cf5534d6b9b70bf8af28ac0dc6
https://doi.org/10.1016/j.fusengdes.2013.01.004

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Manufacture of first wall mock-ups with calibrated defects for fabrication control methods: Development of UT detectable defects

Autor: P. Lorenzetto, B. Boireau, O. Burat, A. Cottin, F. Lepers, F. Zacchia, I. Bobin

Publikováno v: Fusion Engineering and Design. 87:1425-1433

A Research and Development program for the ITER Blanket-First Wall has been implemented in Europe to provide input data for the manufacture of the full-scale production components. In this frame, FW mock-ups have been fabricated according to ITER FW

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::9b4a97c124b9e846d35879999b1cbcfd
https://doi.org/10.1016/j.fusengdes.2012.03.025

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High heat flux testing of beryllium components with improved diagnostics

Autor: C. Thomser, F. Zacchia, B. Bellin, A. Buerger, M. Roedig, Jochen Linke, A. Schmidt

Publikováno v: Fusion Engineering and Design. 86:2409-2412

Beryllium is one of the most interesting materials to be used in nuclear fusion devices due to its promising properties. However, testing of beryllium components is quite challenging because of its toxicity and the required safety procedures. Within

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::7c165e9c6b51aba2a7a7d997ecba07ee
https://doi.org/10.1016/j.fusengdes.2011.01.102

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