A model for uniform Zircaloy clad corrosion in pressurized water reactors-Reference-Cited by-同舟云学术

A model for uniform Zircaloy clad corrosion in pressurized water reactors

Published:1995-03 Issue:2 Volume:154 Page:157-168
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Forsberg K.,Limbäck M.,Massih A.R.

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

Reference20 articles.

1. An Introduction to Solid State Diffusion;Borg,1988

2. The Oxidation and Corrosion of Zirconium and its Alloys

3. A model for the oxidation of zirconium-based alloys

4. Review of PWR fuel rod waterside corrosion behavior;Garzarolli;EPRI NP-1472,1979

Cited by 13 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 inadequacy in fuel performance code calibration: Derivative-based parameter uncertainty inflation;Annals of Nuclear Energy;2024-12

2. A corrosion model for CZ cladding based on in-pile irradiation data;Frontiers in Energy Research;2024-05-23

3. Duplex and Optimized ZIRLO™ Fuel Cladding Experience in a European High-Duty Pressurized Water Reactor;Zirconium in the Nuclear Industry: 20th International Symposium;2023-11-01

4. Performance evaluation of thermal conductivity models for fission gases with application to UO2-zirconium dispersion fuel;Annals of Nuclear Energy;2023-06

5. Treating model inadequacy in fuel performance model calibration by parameter uncertainty inflation;Annals of Nuclear Energy;2022-12