Effect of high-temperature water and hydrogen on the fracture behavior of a low-alloy reactor pressure vessel steel

Supratik Roychowdhury (Corresponding Author), Hans Peter Seifert, Philippe Spätig, Zaiqing Que

Research output: Contribution to journalArticleScientificpeer-review

15 Citations (Scopus)

Abstract

Structural integrity of reactor pressure vessels (RPV) is critical for safety and lifetime. Possible degradation of fracture resistance of RPV steel due to exposure to coolant and hydrogen is a concern. In this study tensile and elastic-plastic fracture mechanics (EPFM) tests in air (hydrogen pre-charged) and EFPM tests in hydrogenated/oxygenated high-temperature water (HTW) was done, using a low-alloy RPV steel. 2–5 wppm hydrogen caused embrittlement in air tensile tests at room temperature (25 °C) and at 288 °C, effects being more significant at 25 °C and in simulated weld coarse grain heat affected zone material. Embrittlement at 288 °C is strain rate dependent and is due to localized plastic deformation. Hydrogen pre-charging/HTW exposure did not deteriorate the fracture resistance at 288 °C in base metal, for investigated loading rate range. Clear change in fracture morphology and deformation structures was observed, similar to that after air tests with hydrogen.
Original languageEnglish
Pages (from-to)343-364
JournalJournal of Nuclear Materials
Volume478
DOIs
Publication statusPublished - 2016
MoE publication typeA1 Journal article-refereed

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