Modelling of fuel rod behaviour and recent advances of the transuranus code-Reference-Cited by-同舟云学术

Modelling of fuel rod behaviour and recent advances of the transuranus code

Published:1988-03 Issue:3 Volume:106 Page:291-313
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Lassmann K.,Blank H.

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

Reference116 articles.

1. International Conference on Structural Mechanics in Reactor Technology: 1st SMiRT,1971

2. International Conference on Structural Mechanics in Reactor Technology: 2nd SMiRT,1973

3. International Conference on Structural Mechanics in Reactor Technology: 3rd SMiRT,1975

4. International Conference on Structural Mechanics in Reactor Technology: 4th SMiRT,1977

5. International Conference on Structural Mechanics in Reactor Technology: 5th SMiRT,1979

Cited by 42 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. Deep heterogeneous joint architecture: A temporal frequency surrogate model for fuel performance codes;Annals of Nuclear Energy;2025-02

2. An assessment of UO2 and ATF concept fuel performance modeling demands against current experimental capabilities under LOCA conditions;Annals of Nuclear Energy;2024-09

3. Investigation on radial fuel relocation and its influence on heat split phenomenon of dual-cooled annular fuel element;International Journal of Advanced Nuclear Reactor Design and Technology;2022-09

4. Investigation on fuel cracking induced relocation behavior of dual-cooled annular fuel based on finite element simulation;Journal of Nuclear Materials;2022-08

5. Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System;Frontiers in Energy Research;2021-10-15