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| Автори: Димова, Г. Т. Заглавие: А Study for Measuring Core barrel Swelling in Nuclear Power Plants Caused by Operating Conditions Ключови думи: Nuclear Reactor, Swelling, Radiation, Embrittlement. Абстракт: The policy of each NPP is to ensure safe production of electrical energy as well as security of supply. The metal of NPP equipment is influenced of aging mechanisms from the working environment – neutron and thermal brittleness, corrosion, erosion, fatigue and wear. Neutron flux causes the most damaging effect on the metal structure. After prolonged periods of exposure to high-energy neutrons (several decades), the metal of the reactor vessel becomes brittle and strengthened, and defects are expected to appear and develop in the structure, which further fragile the metal. Temperature and dose load gradients can cause swelling of the metal of the reactor internals. In this 'worst-case scenario', the distance between the core barrel and the fuel roads is expected to be reduced, to disturb the movement of the heat carrier and the heat balance, to obtain jamming and blocking of units of the reactor control and protection system. At the same time, neither the regulatory framework nor the t Библиография Издание
Издателските права се държат от International Journal of Current Research Пълен текст на публикацията | Autors: Dimova, G. T. Title: А Study for Measuring Core barrel Swelling in Nuclear Power Plants Caused by Operating Conditions Keywords: Nuclear Reactor, Swelling, Radiation, Embrittlement. Abstract: The policy of each NPP is to ensure safe production of electrical energy as well as security of supply. The metal of NPP equipment is influenced of aging mechanisms from the working environment – neutron and thermal brittleness, corrosion, erosion, fatigue and wear. Neutron flux causes the most damaging effect on the metal structure. After prolonged periods of exposure to high-energy neutrons (several decades), the metal of the reactor vessel becomes brittle and strengthened, and defects are expected to appear and develop in the structure, which further fragile the metal. Temperature and dose load gradients can cause swelling of the metal of the reactor internals. In this 'worst-case scenario', the distance between the core barrel and the fuel roads is expected to be reduced, to disturb the movement of the heat carrier and the heat balance, to obtain jamming and blocking of units of the reactor control and protection system. At the same time, neither the regulatory framework nor the t References Issue
Copyright International Journal of Current Research Full text of the publication |
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