Experimental insights on iron-based alloys corrosion in water cooled loops

被引:0
|
作者
Molinari, Martina [1 ]
Lo Piccolo, Eugenio [2 ]
Torella, Raffaele [2 ]
D'Onorio, Matteo [1 ]
Terranova, Nicholas [3 ]
Caruso, Gianfranco [1 ]
机构
[1] Sapienza Univ Rome, Dept Astronaut Elect & Energy Engn DIAEE, Nucl Sect, Corso Vittorio Emanuele II 244, I-00186 Rome, Italy
[2] RINA Consulting Ctr Siluppo Materiali SpA Roma, Via Castel Romano 100, I-00128 Rome, Italy
[3] ENEA Fus & Technol Nucl Safety & Secur Dept, Via Enrico Fermi 45, I-00044 Frascati, Italy
关键词
Potassium hydroxide; Oxygen control; Corrosion; Corrosion tests; EUROFER; High-temperature high-pressure;
D O I
10.1016/j.nme.2024.101786
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This paper presents experimental findings on the behavior of iron-based alloys in environmental conditions typical of nuclear fusion technology, specifically focusing on material degradation, which is a critical aspect for the water cooling system of EU DEMO breeding blankets. The experimental campaign investigates potassium hydroxide's role as an alkalizing agent, testing various concentrations to assess its impact on corrosion resistance. Additionally, it examines how oxygen levels affect localized corrosion development, which is crucial for mitigating corrosion risks in fusion applications. Seven 1000-hour tests were conducted to determine optimal conditions for corrosion reduction. Findings include identifying an oxygen concentration threshold to prevent piping cracking on EUROFER97 specimens.
引用
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页数:10
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