Comparative studies on high-temperature corrosion of ZrNb1 and Zircaloy-4-Reference-Cited by-同舟云学术

Comparative studies on high-temperature corrosion of ZrNb1 and Zircaloy-4

Published:1994-01 Issue:1 Volume:147 Page:53-62
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Böhmert J.,Dietrich M.,Linek J.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference10 articles.

1. Untersuchungen zur Hochtemperatur-Dampfoxidation von ZrNb1;Böhmert,1991

2. Kinetik und Morphologie der isothermen Dampf-Oxidation von Zircaloy 4 bei 700–1300°C;Leistikow;Kernforschungszentrum Karlsruhe, KfK 2587,1978

3. Untersuchungen über das Erscheinungsbild und die kinetischen Folgen gestörter Deckschichtbildung bei der Zircaloy-4/Wasserdampf-Hochtemperatur-Oxidation;Bennek-Kammerichs,1980

4. Microstructural reasons for mechanical oxide degradation;Schanz,1981

5. Oxidation of Zircaloy-4 under limited steam supply at 1000 and 1300°C;Uetsuka,1984

Cited by 33 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Understanding the oxidation resistance of zirconium alloy at 1000°C based on the formation of a Zr-Sn intermetallic phase and co-precipitation of Sn and Nb;Acta Materialia;2024-02

2. MAGNESIUM-THERMAL METHOD OF SPONGE ZIRCONIUM OBTAINING;Problems of Atomic Science and Technology;2024-01-29

3. The modeling of interaction between fuel element cladding and steam;Nuclear Engineering and Design;2023-08

4. Study on the integrity of prolonged steam oxidized clad column quenched at various reflood rates;Nuclear Engineering and Design;2023-02

5. Effects of elevated temperature steam oxidation and subsequent quenching on light water reactor clad;Progress in Nuclear Energy;2023-01