Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels-Reference-Cited by-同舟云学术

Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels

Published:2016-08 Issue: Volume:305 Page:559-568
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Brankov Vladimir,Khvostov Grigori,Mikityuk Konstantin,Pautz Andreas,Restani Renato,Abolhassani Sousan,Ledergerber Guido,Wiesenack Wolfgang

Funder

PSI

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

Reference21 articles.

1. Modelling of Zircaloy-4 Cladding Behaviour at High Burnup, Nuclear Fuel Behaviour Modelling at High Burnup and its Experimental Support;Bang,2001

2. Observation of a Pellet-Cladding Bonding Layer in High Power Fuel;Berghe,2004

3. Irradiation-enhanced Deformation of Zr-2.5Nb Tubes at High Neutron Fluences;Causey,2000

4. Assessment of fuel rod performance codes under ramp scenarios investigated within the SCIP project;Herranz;Nucl. Eng. Des.,2011

5. High-Burnup-Fuel Technical and Economical Lessons Learned at Swiss Nuclear Power Plants;Jatuff,2013

Cited by 10 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. Interpretation of the online measurement data for selected tests of the RISOE-III project;Journal of Nuclear Materials;2024-10

2. Evaluation on Thermodynamic Compatibility between High Density Ceramic Nuclear Reactor Fuels Ux(X=C,N) and Light Water Reactor Cladding Materials (Zr and Sic);2024

3. Modelling effects of transient FGR in LWR fuel rods during a LOCA;Journal of Nuclear Materials;2022-02

4. FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits;Nuclear Engineering and Technology;2021-11

5. Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage;Kerntechnik;2020-06-01