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Fusion
Published in William J. Nuttall, Nuclear Renaissance, 2022
The intergovernmental collaborative approach to fusion has first proposed an International Fusion Materials Irradiation Facility (IFMIF) in 1994. As talk of a fast-track grew, the need for such a machine became compelling, but actual progress was painfully slow. In 2021, the device is only partly developed by a Japanese-Euratom consortium [87]. Meanwhile, at the Culham in the United Kingdom, the original home of fast-track thinking, a set of underpinning technology-oriented laboratories have been established including—the National Nuclear User Facility’s Materials Research Facility [88] and the Hydrogen-3 Advanced Technology (H3AT) facility dedicated to the processing, storage and recycle tritium for fusion applications [89].
Modular global uncertainty analysis of event-driven indicators of system’s availability
Published in Stein Haugen, Anne Barros, Coen van Gulijk, Trond Kongsvik, Jan Erik Vinnem, Safety and Reliability – Safe Societies in a Changing World, 2018
Pawel M. Stano, Michal Spirzewski
The practical implementation of the proposed GUA procedure is illustrated on an example, which involves the analysis of the model of the Injector System within the International Fusion Materials Irradiation Facility (IFMIF). The IFMIF is an accelerator-based neutron source, developed jointly by Europe and Japan, which is conceived for fusion materials testing. The main purpose of the Injector System of the linear accelerator under study is to deliver sufficient beam current to the first accelerating cavity (RFQ—Radio Frequency Quadrupole) (Bargallo Font, 2014), and thus to achieve a 125 mA RFQ output current. The Injector is composed of four subsystems: Source and Extraction System (SES); Low Energy Beam Transport (LEBT); Local Control System (LCS); and Auxiliaries System (AUX), which are connected sequentially reliability-wise. Thus, in case of the analyzed Injector, the GUA decomposition into modes naturally overlaps with the decomposition into subsystems.
Global Flux Calculation for IFMIF-DONES Test Cell Using Advanced Variance Reduction Technique
Published in Fusion Science and Technology, 2018
The IFMIF-DONES (International Fusion Materials Irradiation Facility–DEMO Oriented NEutron Source1,2) is a downscaled IFMIF-based neutron irradiation facility which aims at providing the irradiation data required for the construction of a DEMO fusion power plant. DONES consists of only one of the IFMIF accelerators (40 MeV and 125 mA) and utilizes only the High Flux Test Module (HFTM) for the irradiation of material specimens. This facility produces intense neutrons with a neutron flux up to 1015 n/cm2/s and energy up to 55 MeV at the target. The shielding of the facility is very important for the test cell (TC) design. The DONES TC design is based on the design developed during the IFMIF/Engineering Validation and Engineering Design Activities (EVEDA) phase. The heavy concrete bioshield of the TC housing the irradiation test modules is up to 4 m thick. The biological dose rate distribution outside the bioshield needs to be known with sufficient accuracy for assessing the accessibility during operation and maintenance periods of the facility.