Release and deposition of corrosion products in a simulated BWR coolant system
Creators
- 1. Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan). Komae Research Lab.
Description
Information on corrosion products release from structural material is useful for radiation control in reactor coolant systems. The influence of dissolved oxygen on corrosion products release from AISI 304 stainless steel was studied in high purity water from 30 deg C to 280 deg C which corresponds to the state of BWR coolant system. The release rates of Fe, Ni and Co from stainless steel increased as the temperature was raised from 30 deg C and reached the maximum at about 200 deg C, then decreased as the temperature was raised. Their release rates were reduced by the addition of dissolved oxygen in about 100 μg/kg at the temperatures in this experiment. On the other hand, the release rate of Cr was maintained at low levels at temperature up to 280 deg C, when the concentration of dissolved oxygen was below 1 mg/kg. With the concentration of dissolved oxygen exceeding 1 mg/kg, the Cr was released as chromium anion, especially at high temperatures. This release behavior was possibly caused by the dissolution of chromium-rich films. Accumulation of ionic Co on the zircaloy surface was examined under simulated BWR primary coolant condition using 58Co as a tracer. Among Fe, Cr and Ni components, Cr component showed highest deposition rate on the zircaloy surface. 58Co was likely to be present in this Cr deposits. The rate of 58Co accumulation was reduced on the pretreated zircaloy with overheated steam to form stable ZrO2 films. Behavior of ionic Co can be explained by the interaction with Cr component. (author)
Additional details
Publishing Information
- Publisher
- Japan Atomic Industrial Forum.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of 1988 JAIF international conference on water chemistry in nuclear power plants
- Imprint Pagination
- 843 p.
- Journal Page Range
- v. 2 p. 367-372.
Conference
- Title
- 1988 JAIF international conference on water chemistry in nuclear power plants.
- Dates
- 19-22 Apr 1988.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 20037761
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COBALT COMPOUNDS; CORROSION PRODUCTS; DEPOSITION; HIGH TEMPERATURE; IRON COMPOUNDS; MEDIUM TEMPERATURE; NICKEL COMPOUNDS; OXYGEN; PIPES; PRIMARY COOLANT CIRCUITS; QUANTITY RATIO; RADIATION DOSES; STEEL-CR19NI10; TEMPERATURE DEPENDENCE; WATER CHEMISTRY; ZIRCALOY
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COOLING SYSTEMS; CORROSION RESISTANT ALLOYS; ELEMENTS; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; NICKEL ALLOYS; NONMETALS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STAINLESS STEELS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WATER TREATMENT; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- Imprint:Composed of two volumes.