Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Corrosion resistance of structure materials in lead coolant with reference to reactor installation BREST-OD-300

A. Roussanov, V. Troyanov, G. Jachmenev, A. Demishonkov

Abstract

Systematic researches for lead coolant have been performed from the beginning of 1990s within the framework of development of activities on the BREST-OD-300 reactor installation. The main type of corrosion damages in lead and lead-bismuth coolant is the local dissolution of structure materials (steels) and their components and then in those structure materials and components. The main results for ensuring high corrosion-erosive stability of materials in heavy metal coolant are given by the application of silicon-containing steels, the passivation oxygen, and the application of additional corrosion barrier as oxide films on the surface of structure elements. Various researches of corrosion behaviors of steels in lead coolant based on those results are under way. The experience gained so far allows to forecast the absence of corrosion damages of steels in lead-bismuth coolant up to 620 oC on the basis of tens thousand hours that was proved by successful experience of reactor installation activities. The obtained results from the test at higher temperature showed a good fuel-cladding compatibility.

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key words: Fast Neutron Spectrum Systems, Nuclear Technology
Reference:
Advisory Group Meeting on “Design and Performance of Reactor and Sub-critical Blanket Systems with Lead and Lead-Bismuth as Coolant and/or Target Material” , Moscow, Russian Federation, 23-27 October 2000
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1348, pp:122-124