Effect of Surface Treatment on the Irradiation Enhancement of Corrosion of Zircaloy-2 in HBWR


Book Description

Specimens of Zircaloy-2 have been exposed at 240°C (464°F) in various locations in the primary circuit of the Halden Boiling Water Reactor (HBWR). Corrosion data have also been collected from Zircaloy-2 clad fuel elements. The radiation field caused a drastic enhancement of the attack, corrosion rates increased a hundred times, and was under normal conditions about 0.15 mg/dm2 per day for pickled, anodized, and autoclaved material. Variations in the flux level from 2 x 109 to 3 x 1012 neutrons (n)/cm2 . s (> 1 MeV) had little influence on the corrosion rate, and it is suggested that ?-irradiation or lower energy neutrons, rather than fast neutrons, can be responsible for the corrosion enhancement. When uranium was present in the water, the corrosion rate increased for pickled and for autoclaved fuel rods, while hardly any effect was observed with anodized material. A deliberate fluoride contamination on the specimens increased the corrosion rate in-pile as well as out-of-pile. By anodizing this harmful effect of fluorides could be completely counteracted.










Advances in Corrosion Science and Technology


Book Description

This series was organized to provide a forum for review papers in the area of corrosion. The aim of these reviews is to bring certain areas of corrosion science and technology into a sharp focus. The volumes of this series are published approximately on a yearly basis and each contains three to five reviews. The articles in each volume are selected in such a way as to be of interest both to the corrosion scientists and the corrosion technologists. There is, in fact, a particular aim in juxtaposing these interests because of the importance of mutual interaction and interdisciplinarity so important in corrosion studies. It is hoped that the corrosion scientists in this way may stay abreast of the activities in corrosion technology and vice versa. In this series the term "corrosion" is used in its very broadest sense. It includes, therefore, not only the degradation of metals in aqueous en vironment but also what is commonly referred to as "high-temperature oxidation. " Further, the plan is to be even more general than these topics; the series will include all solids and all environments. Today, engineering solids include not only metals but glasses, ionic solids, polymeric solids, and composites of these. Environments of interest must be extended to liquid metals, a wide variety of gases, nonaqueous electrolytes, and other non aqueous liquids.







Structural Materials in Nuclear Power Systems


Book Description

In recent years the effort devoted to assuring both the safety and reliability of commercial nuclear fission power reactors has markedly increased. The incentives for performing this work are large since the resulting im provement in plant productivity translates into lower fuel costs and, more importantly, reduced reliance on imported oil. Reliability and availability of nuclear power plants, whether fission or fusion, demand that more attention be focused on the behavior of materials. Recent experiences with fission power indicate that the basic properties of materials, which categorize their reliable behavior under specified conditions, need reinforcement to assure trouble-free operation for the expected service life. The pursuit of additional information con tinues to demand a better understanding of some of the observed anom alous behavior, and of the margin of resistance of materials to unpre dictable service conditions. It is also apparent that, next to plasma heating and confinement, materials selection represents the most serious chal lenge to the introduction of fusion power. The recognition of the importance of materials performance to nu clear plant performance has sustained a multimillion dollar worldwide research and development effort that has yielded significant results, both in quantification of the performance limits of materials in current use and the development and qualification of new materials. Most of this infor mation appears in the open literature in the form of research reports, journal articles, and conference proceedings.