Research the behaviour and properties of WWER type fuel claddings from Zr1%Nb alloy in loss of the coolant accident

• Date: 2021
• Main Authors: Semerak, M.M., Lys, S.S.
• Format: Article
• Language: English
• Published: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2021
• Series: Вопросы атомной науки и техники
• Subjects: Thermal and fast reactor materials
• Online Access: http://dspace.nbuv.gov.ua/handle/123456789/194896
• Journal Title: Digital Library of Periodicals of National Academy of Sciences of Ukraine
• Cite this: Research the behaviour and properties of WWER type fuel claddings from Zr1%Nb alloy in loss of the coolant accident / M.M. Semerak, S.S. Lys // Problems of Atomic Science and Technology. — 2021. — № 2. — С. 80-86. — Бібліогр.: 9 назв. — англ.

The paper presents safety criteria placed on fuel rod condition in loss of the coolant accident (LOCA) conditions as applied to reactor plants with WWER. The paper reveals briefly experimental studies carried out to validate safety criteria (acceptance criteria). The scope of the data experimentally obtained by research the behaviour and properties of WWER type fuel claddings from Zr1%Nb alloy under loading conditions simulating the stage of core flooding with water in LOCA suffices to judge the character and numerical value of criterional parameters of the embrittlement criterion in terms of the cladding stability upon flooding and subsequent implementation of fuel assembly (FA) unloading and transportation. Accidents are considered involving loss of coolant by primary circuit which are characterized by conditions of degraded heat transfer from fuels. During accidents loss of tightness by fuel rod cladding is tolerable, however, in this case, the cooling of a distorted fuel rod and the dismantling (unloading) of the core after an accident have to be feasible.