Published June 1995 | Version v1
Journal article Metadata-only

Crevice corrosion characteristics of Zr-2.5wt%Nb alloy and SUS403Mod in high temperature pure water

Creators

  • 1. Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center

Description

Crevice corrosion characteristics of 13% chromium martensitic stainless steel bearing 3.5% nickel and zirconium alloy containing 2.5% niobium (Zr-2.5wt%Nb) were investigated in high temperature pure water. Corrosion of the stainless steel occurred in the crevice, while corrosion of the Zr-2.5wt%Nb was inhibited. Corrosion pits were formed on the stainless steel in the early period of the corrosion test. However, these pits were repassivated in the subsequent corrosion test and the pits did not propagate. The Zr-2.5wt%Nb alloy absorbs the hydrogen generated by the corrosion of the stainless steel and the hydrogen pick up is correlated with the corrosion of the stainless steel. (author)

Availability note (English)

Available from DOI: https://doi.org/10.3327/jaesj.37.526

Abstract (Japanese)

新型転換炉(ATR)の炉心の圧力管には燃料集合体が収納されており、その中を軽水が1次冷却水として流れる。ステンレス鋼のすき間腐食に関する研究は少なく、ステンレス鋼あるいはステンレス鋼とZr合金のすき間腐食に関する具体的な研究も少ない。現在、ATRで用いられているSUS403ModやZr-2.5Nbに腐食が問題となっているものはないが、ロールドジョイント構造の長期間の安全性を把握する意味で、腐食データの積重ねは重要なことである。本報においては、Zr-2.5Nbの高温純水中(288℃)におけるZr-2.5Nb単体の腐食とZr-2.5NbとSUS403Modとのすき間腐食について検討した。これらについて以下に報告する。(日本)

Additional details

Additional titles

Original title (Japanese)
高温純水中のZr-2.5wt%Nb合金とSUS403Modのすき間腐食

Identifiers

DOI
10.3327/jaesj.37.526;

Publishing Information

Journal Title
Nippon Genshiryoku Gakkai-Shi
Journal Volume
37
Journal Issue
6
Journal Page Range
p. 526-534
ISSN
0004-7120

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
54066534
Subject category
S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ABSORPTION; BENCH-SCALE EXPERIMENTS; CHROMIUM ALLOYS; CREVICE CORROSION; HYDROGEN; JATR REACTOR; PRESSURE TUBES; TEMPERATURE RANGE 0400-1000 K; WATER; ZIRCONIUM ALLOYS
Descriptors DEC
ALLOYS; CHEMICAL REACTIONS; CORROSION; ELEMENTS; HEAVY WATER MODERATED REACTORS; HWLWR TYPE REACTORS; HYDROGEN COMPOUNDS; NATURAL URANIUM REACTORS; NONMETALS; OXYGEN COMPOUNDS; PLUTONIUM REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SORPTION; TEMPERATURE RANGE; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TUBES; WATER COOLED REACTORS

Optional Information

Notes
This record replaces 26067203