Corrosion behavior of stainless steels under heat transfer condition in simulated solution of dissolver for FBR fuel reprocessing.

Hayashi, Syotaro; Ojima, Hisao; Kawaguchi, Katsuyuki; Shinohara, Masatomo; Kawano, Takayuki

doi:10.3327/jaesj.31.1273

Cited by 4 publications

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“…With respect to NO, Hayashi investigated the influence of NO injection on the corrosion rate of SS310 Nb (25?2%Cr, 20?4%Ni, 0?2%Nb and 0?013%C) in a solution to simulate that used for fuel reprocessing (4 N HNO 3 /8?5 g L 21 V z5 /1?2 g L 21 Ce z2 ). 32 The highest corrosion rates were found in NO free solution. NO injection decreased corrosion rates in boiling solution by more than a factor of 10, from 0?5 g m 22 h 21 (600 mm year 21 ) to 0?02 g m 22 h 21 (20 mm year 21 ) (Fig.…”

Section: Corrosion In Off-gas Extraction Systemmentioning

confidence: 97%

A review of corrosion issues related to uranyl nitrate base aqueous homogeneous reactors

Lillard

2010

Corrosion Engineering, Science and Technology

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Aqueous homogeneous reactors (AHRs) are liquid fuel nuclear reactors, typically consisting of an acidified nitrate or sulphate base solution of enriched uranium-235 ( 235 U). The goal of this paper is to review both the report and research literature on the topic of materials corrosion issues related to uranyl nitrate base AHRs. The materials of interest are stainless steel (SS)347, SS304L, SS304L-NAG, SS316L and zirconium (Zr) base alloys. In nitric acid solutions, SS and Zr alloys are passive, although there is some increased susceptibility of SS347 to intergranular corrosion (IGC) and knife-line attack as compared to other alloys. This is likely a result of the higher carbon (C) content in SS347. In uranyl nitrate fuel simulants corrosion rates increased as compared with nitric acid alone with the corrosion rate of SS347 being the highest while SS316 was the lowest of the austenitic stainless steels tested. In comparison, corrosion rates of Zr based alloys remained relatively unchanged in uranyl nitrate base solutions. The most prominent issue for these materials appears to be iodide (I 2 ) induced pitting corrosion on the walls of the off-gas extraction system with the potential for stress corrosion cracking. For Zr alloys, vapour phase I 2 pitting and SCC are well documented failure mechanisms with the threshold I 2 concentration being on the order of 1-2 ppm. In the off-gas extraction system of a 200 kW AHR calculations indicate that the I 2 concentration may be as high as 0?4-0?6 ppm warranting further study in this area. The influence of a prototypic AHR neutron flux on corrosion rates and susceptibility to underfilm corrosion, due to precipitation of UO 2 (OH) 2 , was not available from the literature.

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Section: Corrosion In Off-gas Extraction Systemmentioning

confidence: 97%

A review of corrosion issues related to uranyl nitrate base aqueous homogeneous reactors

Lillard

2010

Corrosion Engineering, Science and Technology

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Corrosion in Nuclear Fuel Reprocessing Plants: Corrosion in Boiling Nitric Acid

Kato

2020

Comprehensive Nuclear Materials

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Corrosion Behavior of Stainless Steel in Nitric Acid Solutions Including Neptunium

Motooka¹,

Yamamoto²

2008

ZAKAEP

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In order to investigate a corrosion behavior of stainless steel in the typical nuclear fuel reprocessing plant, corrosion tests using nitric acid solution with neptunium were conducted under atmospheric and the reduced pressure conditions in the laboratory where radioactive substance could be handled. An ultra low carbon type of SUS304ULC stainless steel was used. Obtained results were as follows: Under the reduced pressure condition, corrosion of the stainless steel was accelerated in the nitric acid solution with neptunium than in pure nitric acid solution. Under an atmospheric condition, the corrosion rate of the stainless steel increased with increase of neptunium content. The higher solution temperature enhanced the corrosion rate of the stainless steel in the nitric acid solution with neptunium. Thermodynamic data showed that Np(V) oxidized to Np(VI) by concentrated and elevated nitric acid solution. The corrosion potential of the stainless steel shifted to nobler direction in the nitric acid solution with neptunium. It is estimated that the electrochemical reaction of Np(VI)/Np(V) is reversible and the rate constant of the reaction has great values. And it is considered that the dominance of Np(VI) in nitric acid solution accelerated the corrosion rate of the stainless steel in the solutions with neptunium.

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Corrosion behavior of stainless steels under heat transfer condition in simulated solution of dissolver for FBR fuel reprocessing.

Cited by 4 publications

References 0 publications

A review of corrosion issues related to uranyl nitrate base aqueous homogeneous reactors

A review of corrosion issues related to uranyl nitrate base aqueous homogeneous reactors

Corrosion in Nuclear Fuel Reprocessing Plants: Corrosion in Boiling Nitric Acid

Corrosion Behavior of Stainless Steel in Nitric Acid Solutions Including Neptunium

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