European supercritical water cooled reactor

Schulenberg, Thomas S.; Starflinger, Jörg; Marsault, P.; Bittermann, D.; Maráczy, Cs.; Laurien, Eckart; Nijeholt, J.A. Lycklama à; Anglart, Henryk; Andreani, Michele; Ruzickova, M.; Toivonen, Aki

doi:10.1016/j.nucengdes.2010.09.039

Cited by 54 publications

(10 citation statements)

References 5 publications

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“…N50 was investigated in comparison to SS316 due to its higher concentration of Cr and Mn, that results in higher yield strength and better corrosion resistance compared to SS316 [17][18][19]. SS316 was chosen for comparison due to its frequent use in the nuclear and coal industries and is generally considered the benchmark 3 standard [20]. Experimentation was conducted using the supercritical water loop (SCWL) facility at the University of Nevada, Reno.…”

Section: Introductionmentioning

confidence: 99%

Oxidation of stainless steel 316 and Nitronic 50 in supercritical and ultrasupercritical water

Rodriguez

Chidambaram

2015

Applied Surface Science

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Corrosion of stainless steel 316 and Nitronic 50 exposed to supercritical and ultrasupercritical water was studied as a function of temperature and exposure time. Post-exposure surface analysis was performed using Raman and X-ray photoelectron spectroscopies to determine the chemistry of the oxides formed as a result of the exposure. When exposed to supercritical water, Nitronic 50 and stainless steel 316 were observed to have similar weight gains; however, stainless steel 316 was found to gain less weight than Nitronic 50 in exposure tests performed in ultrasupercritical water. Stainless steel 316 developed surface films primarily composed of iron oxides, while the surface of Nitronic 50 contained a mixture of iron, chromium and manganese oxides. Based on these analyses, the differences in weight gain and oxidation characteristics of the two materials are attributed to the higher concentration of Cr and Mn in Nitronic 50 compared to stainless steel 316.

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Section: Introductionmentioning

confidence: 99%

Oxidation of stainless steel 316 and Nitronic 50 in supercritical and ultrasupercritical water

Rodriguez

Chidambaram

2015

Applied Surface Science

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“… General corrosion tests in supercritical water environment are needed to progress in the design, analysis and licensing of a fuel assembly cooled with supercritical water in a research reactor [2] . The austenitic stainless steels tested are candidate materials for structural components of the European Generation IV Supercritical Water reactor concept [3] . Microstructural and chemical analysis of the oxide, bulk and grain boundaries may provide indications about materials performances and possible failure mechanisms.…”

Section: Value Of the Datamentioning

confidence: 99%

Corrosion and microstructural analysis data for AISI 316L and AISI 347H stainless steels after exposure to a supercritical water environment

et al. 2016

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This article presents corrosion data and microstructural analysis data of austenitic stainless steels AISI 316L and AISI 347H exposed to supercritical water (25 MPa, 550 °C) with 2000 ppb of dissolved oxygen. The corrosion tests lasted a total of 1200 h but were interrupted at 600 h to allow measurements to be made. The microstructural data have been collected in the grain interior and at grain boundaries of the bulk of the materials and at the superficial oxide layer developed during the corrosion exposure.

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“…The next investigations were performed on the European concept of the supercritical water cooled reactor, the HighPerformance Light Water Reactor (HPLWR) (Schulenberg et al, 2011). The thermal power of HPLWR is 2300 MW (power density is about 28.1 MW/t-HM) and the efficiency is 43e44%.…”

Section: Scwrmentioning

confidence: 99%