Corrosion study of heat exchanger tubes in pressurized water cooled nuclear reactors by conversion electron Moessbauer spectroscopy
Creators
- 1. Department of Nuclear Chemistry, Eoetvoes University, Budapest (Hungary)
- 2. Research Group for Nuclear Medthods in Structural Chemistry, Hungarian Academy of Sciences, Eoetvoes University, Budapest (Hungary)
- 3. Department of Radiochemistry, University of Veszprem, Veszprem (Hungary)
- 4. Paks NPP, Paks (Hungary)
Description
Nuclear energy production tends to return into the focus of interest because of the constantly increasing energy need of the world and the green house effect problems of the strongest competitor oil or gas based power plants. In addition to the construction of new nuclear power plants, lifetime extension of the existing ones is the most cost effective investment in the energy business. However, feasibility and safety issues become very important at this point, and corrosion of the construction materials should be carefully investigated before decision on a potential lifetime extension of a reactor. 57Fe-Conversion Electron Moessbauer Spectroscopy (CEMS) is a sensitive tool to analyze the phase composition of corrosion products on the surface of stainless steel. The upper ∼300 nm can be investigated due to the penetration range of conversion electrons. The corrosion state of heat exchanger tubes from the four reactor units of the Paks Nuclear Power Plant, Hungary, were analyzed by several methods including CEMS. The primary circuit side of the tubes was studied on selected samples cut out from the heat exchangers during regular maintenance. Cr- and Ni-substituted magnetite, sometimes hematite, amorphous Fe-oxides/oxyhydroxides as well as the signal of bulk austenitic steel of the tubes were detected. The level of Cr- and Ni-substitution in the magnetite phase could be estimated from the Moessbauer spectra. Correlation between earlier decontamination cycles and the corrosion state of the heat exchangers was sought. In combination with other methods, a hybrid structure of the surface oxide layer of several microns was established. It is suggested that previous AP-CITROX decontamination cycles can be responsible for this structure which makes the oxide layer mobile. This mobility may be responsible for unwanted corrosion product transport into the reactor vessel by the primary coolant.
Additional details
Publishing Information
- Imprint Title
- Abstracts book: asia-pacific symposium on radiochemistry-05 (APSORC-05)
- Imprint Pagination
- 360 p.
- Journal Page Range
- p. 261
Conference
- Title
- 3. asia-pacific symposium on radiochemistry
- Dates
- 17-21 Oct 2005
- Place
- Beijing (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 44055564
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AUSTENITIC STEELS; CONSTRUCTION; CORROSION; CORROSION PRODUCTS; COST; DECONTAMINATION; HEAT EXCHANGERS; INVESTMENT; LIFETIME EXTENSION; MAINTENANCE; MATERIALS; MOESSBAUER EFFECT; NUCLEAR POWER PLANTS; PRIMARY COOLANT CIRCUITS; REACTOR VESSELS; SAFETY; STAINLESS STEELS; TUBES; WATER COOLED REACTORS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CLEANING; CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SERVICE LIFE; STEELS; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS