Thermal, Radiation, and Mechanical Analysis for Unsteady-State Fuel Restructuring of Cylindrical Oxide Elements in Fast Reactors-Reference-Cited by-同舟云学术

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Thermal, Radiation, and Mechanical Analysis for Unsteady-State Fuel Restructuring of Cylindrical Oxide Elements in Fast Reactors

Published:1972-06 Issue:2 Volume:48 Page:139-158
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Cheng C. K.¹,Ma B. M.¹

Affiliation:

1. Department of Nuclear Engineering and Engineering Research Institute Iowa State University, Ames, Iowa 50010

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE72-A22467

Cited by 6 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. Pellet-Cladding Interaction of LMFBR Fuel Elements at Unsteady State: An Introduction to Computer Code ISUNE-5;Journal of Engineering for Power;1981-10-01

2. Transient pellet-cladding interaction of LWR fuel rod — Computer code ISUNE-4;Nuclear Engineering and Design;1980-06

3. Irradiation swelling, creep and thermal-stress analysis of LWR fuel elements, computer code isune-2;Nuclear Engineering and Design;1975-11

4. Irradiation swelling, creep and thermal fatigue behaviors of LMFBR pressure vessels;Journal of the Franklin Institute;1975-02

5. Irradiation swelling, creep, thermal shock and thermal cycling fatigue analysis of cylindrical controlled thermonuclear reactor first wall;Nuclear Engineering and Design;1974-07

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