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G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
Stefan Renger, Sören Alt, Ulrike Gocht, Wolfgang Kästner, André Seeliger, Holger Kryk, Ulrich Harm
Nuclear Technology | Volume 205 | Number 1 | January-February 2019 | Pages 248-261
Technical Paper | doi.org/10.1080/00295450.2018.1499324
Articles are hosted by Taylor and Francis Online.
In a joint research project of the Zittau/Goerlitz University of Applied Sciences, the Technische Universität Dresden, and the Helmholtz-Zentrum Dresden-Rossendorf, the main emphasis is the time-related assignment of simultaneous and interacting mechanisms at zinc sources and zinc sinks at boundary conditions of a loss-of-coolant accident (LOCA) in German pressurized water reactors (PWRs). The required experiments are carried out at semitechnical and laboratory scales.
Zinc is used as a protective coating, e.g., for gratings in the containment, showing high corrosion resistance due to a gradual formation of passivating layers. In contrast, its long-term behavior during LOCA changes significantly under the influence of the coolant chemistry of German PWRs. As a consequence, installations in the containment act as zinc sources. Released zinc ions change the chemical properties of the coolant and could, e.g., lead to layer-forming depositions of zinc borates in the core, which increases the possibility of a hindered heat dissipation. For experimental and methodical investigations of these phenomena, the test rig Zittau flow tray, a scaled sump model of a German PWR, was equipped with a full-length 3 × 3 fuel assembly dummy acting as core model, a preheater, and a cooler component. Nine 4.4-m-long fuel rod dummies simulate the decay heat by internal heating cartridges. This rig design enables experimental investigation of physicochemical mechanisms considering coolant containing boric acid and zinc and their influence on the thermohydraulic processes in the reactor core at post-LOCA boundary conditions. Additional zinc corrosion and zinc borate precipitation studies to elucidate chemical zinc corrosion mechanisms and dependencies of those processes on typical LOCA parameters were carried out using lab-scale corrosion/precipitation test facilities.
The time-dependent zinc release at hot-dip galvanized gratings (HGGs) was investigated regarding their position (e.g., inside or near the leaking jet, freely suspended, or submerged in the coolant) and their surface area as well as the temperature and flow rate of the coolant. The experimental database allows the approximation of corrosion rates in dependence of HGG position and the accident-specific coolant leakage rate as well as first mathematical approaches for the modeling of zinc sources.