Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding

• Veröffentlicht in: Вопросы атомной науки и техники
• Datum: 2022
• Hauptverfasser: Zuyok, V., Rud, R., Tretyakov, M., Rud, N., Kushtym, Y., Dykyy, I., Shevchenko, I., Rostova, H., Shtefan, V.
• Format: Artikel
• Sprache: English
• Veröffentlicht: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2022
• Schlagworte: Thermal and fast reactor materials
• Online Zugang: https://nasplib.isofts.kiev.ua/handle/123456789/195413
• Назва журналу: Digital Library of Periodicals of National Academy of Sciences of Ukraine
• Zitieren: Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding / V. Zuyok, R. Rud, M. Tretyakov, N. Rud, Y. Kushtym, I. Dykyy, I. Shevchenko, H. Rostova, V. Shtefan // Problems of Atomic Science and Technology. — 2022. — № 4. — С. 89-96. — Бібліогр.: 30 назв. — англ.

Basic materials for nuclear fuel rod claddings (Zr+1%Nb and E110 alloys), as well as alternative materials for tolerant fuel rod claddings (Cr18Ni10Тi steel and 42CrNiМo alloy), that are able to maximally prevent the development of severe accidents at nuclear power plants were tested in the high-tem...