IAMBUS-1 — A digital computer code for the design, in-pile performance prediction and post-irradiation analysis of arbitrary fuel rods-Reference-Cited by-同舟云学术

IAMBUS-1 — A digital computer code for the design, in-pile performance prediction and post-irradiation analysis of arbitrary fuel rods

Published:1974-01 Issue:3 Volume:31 Page:309-336
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Wordsworth J.

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

Reference47 articles.

1. Irradiation effects in uranium-dioxide;Lustman,1961

2. Irradiation Effects in Nuclear Fuels;Robertson,1969

3. Theory of columnar grain growth and central void formation in oxide fuel rods;Nichols;J. Nucl. Mater.,1967

4. A new simulation method for investigation of UO2 fuel in a thermal gradient corresponding to reactor conditions;Freund,1970

5. An advanced gas release and swelling subroutine;Poeppel,1971

Cited by 21 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. Development and validation of a new oxide fuel rod performance analysis code for the liquid metal fast reactor;Nuclear Science and Techniques;2022-05

2. Modelling of fuel rod behaviour and recent advances of the transuranus code;Nuclear Engineering and Design;1988-03

3. A contribution to the 1D modelling of fuel element mechanics;Nuclear Engineering and Design;1987-05

4. BEAF - a computer program for analysis of light water reactor fuel rod behavior;Nuclear Engineering and Design;1985-05

5. FARST — A computer code for the evaluation of FBR fuel rod behavior under steady-state/transient conditions;Nuclear Engineering and Design;1984-07