Irradiation swelling, creep and thermal-stress analysis of LWR fuel elements, computer code isune-2-Reference-Cited by-同舟云学术

Irradiation swelling, creep and thermal-stress analysis of LWR fuel elements, computer code isune-2

Published:1975-11 Issue:3 Volume:34 Page:361-378
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ma Benjamin M.

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

Reference30 articles.

1. ISUNE 1 — a computer code for performing thermal, radiation, and mechanical analysis of oxide fuel elements of fast reactor in unsteady state;Cheng;Trans. Amer. Nucl. Soc.,1970

2. Computer code abstract, ISUNE 1;Ma;Nucl. Sci. Eng.,1970

3. Thermal, radiation, and mechanical analysis for fast reactor fuel elements (ISUNE 1A);Ma,1971

4. Thermal, radiation and mechanical analysis — fuel restructuring unsteady state of cylindrical oxide elements in fast reactors;Cheng;Nucl. Sci. Eng.,1972

5. CYGRO-3 — a computer program to determine temperatures, stresses and deformations in oxide fuel rods;Duncombe,1970

Cited by 4 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. Thermal, irradiation and cyclic loading analysis for stress fatigue crack in reactor vessels;International Journal of Pressure Vessels and Piping;1988-01

2. 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

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

4. Some analytical and numerical results for cladded fuel rods subjected to thermo-irradiation induced creep;Nuclear Engineering and Design;1979-12