Published September 2006
| Version v1
Journal article
Possible pathways of the fuel element shell protection against corrosion from heat-exchange lead sublayer
- 1. FGUP VNIINM im. akad. A.A. Bochvara, Moscow (Russian Federation)
Description
An analysis of corrosion processes is accomplished which proceed in a fuel element can of EhP823 ferritic-martensitic steel with a lead sublayer under neutron irradiation in BOR-60 reactor. Threshold values of oxygen content in lead are calculated. Corrosion behavior of steel constituents under reactor operation conditions is considered. Test results are given for fuel can material at 700 deg C under various conditions: with and without UN fuel, in unalloyed lead and in lead doped with steel alloying elements. Methods of corrosion protection are proposed for fuel can inner surface
Abstract (Russian)
Проведен анализ коррозионных процессов в оболочке тепловыделяющего элемента из ферритно-мартенситной стали ЭП823 с подслоем из свинца, протекающих при воздействии нейтронного облучения в реакторе БОР-60. Рассчитаны пороговые значения содержания кислорода в свинце. Рассмотрено коррозионное поведение компонентов стали в условиях работы реактора. Приведены результаты испытаний материала оболочки твэла при 700 град С в различных условиях: при наличии и отсутствии UN топлива, в чистом и легированном компонентами стали свинце. Предложены методы защиты внутренней поверхности оболочки твэла от коррозииAdditional details
Additional titles
- Original title (Russian)
- Возможные пути защиты оболочки твэла от коррозии со стороны теплопередающего свинцового подслоя
Publishing Information
- Journal Title
- Metallovedenie i Termicheskaya Obrabotka Metallov
- Journal Issue
- no.9
- Journal Page Range
- p. 35-38
- ISSN
- 0026-0819
- CODEN
- MTOMAX
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 38002085
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- BOR-60 REACTOR; COATINGS; CORROSION; CORROSION PROTECTION; FERRITIC STEELS; FUEL CANS; HIGH ALLOY STEELS; LEAD; MARTENSITIC STEELS; MIXED NITRIDE FUELS; PLUTONIUM NITRIDES; RADIATION EFFECTS; URANIUM NITRIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; CHEMICAL REACTIONS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; METALS; NITRIDES; NITROGEN COMPOUNDS; NUCLEAR FUELS; PLUTONIUM COMPOUNDS; PNICTIDES; POWER REACTORS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; SOLID FUELS; STEELS; TRANSITION ELEMENT ALLOYS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS
Optional Information
- Notes
- 16 refs., 1 fig.