Cladding oxidation model development based on diffusion equations and a simulation of the monoclinic-tetragonal phase transformation of zirconia during transient oxidation-Reference-Cited by-同舟云学术

Cladding oxidation model development based on diffusion equations and a simulation of the monoclinic-tetragonal phase transformation of zirconia during transient oxidation

Published:2014-08 Issue:1-3 Volume:451 Page:55-64
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

He Xiaoqiang,Yu Hongxing,Jiang Guangming,Dang Gaojian,Wu Dan,Zhang Yu

Funder

Nuclear Safety Institute, Russian Academy of Science

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference22 articles.

1. Zircaloy oxidation by steam (rod-like geometry) ZROX model, ICARE2 V3mod1.

2. Core (COR) Package Reference Manual, NUREG/CR-6119.

3. C.M. Allison, G.A. Bema, Damage Progression Model Theory, SCDAP/RELAP5/MOD 3.1 Code Manual. NUREG/CR-6150, 1995.

4. The Observation of Effects of Finite Specimen Geometry on the Oxidation Kinetics of Zircaloy‐4

5. J. Stuckert, M.S. Veshchunov, Behaviour of Oxide Layer of Zirconium-based Fuel Rod Cladding under Steam Starvation Conditions. FZKA 7373, 2008.

Cited by 9 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. Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere;Journal of Nuclear Materials;2024-02

2. Isothermal experiments on steam oxidation of magnetron-sputtered chromium-coated zirconium alloy cladding at 1200 ℃;Corrosion Science;2022-09

3. Study of high burnup effect on steam oxidation of Zircaloy and its regulatory implications via the developement of a pre-transient oxide model of TRANOX;Journal of Nuclear Materials;2022-08

4. Effect of Steady-State Oxidation on Tensile Failure of Zircaloy Cladding;Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT);2022-06-30

5. Development of oxidation model for zirconium alloy cladding and application in the analysis of cladding behavior under loss of coolant accident;Journal of Nuclear Materials;2022-04