Development of a 3-D FBR fuel bundle-to-duct interaction analysis code marse-Reference-Cited by-同舟云学术

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Development of a 3-D FBR fuel bundle-to-duct interaction analysis code marse

Published:1994-06 Issue:1 Volume:148 Page:53-69
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Itoh K.,Kinjo H.,Mimura Y.

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

Reference10 articles.

1. Life limiting features and technical problems to reach high burn-up in fast reactor fuel;Cecchi,1986

2. D.P. Chan and R.J. Jackson, Fuel pin Bundle and hexagonal duct mechanical interaction, ASME 78-PVP-48, American Society of Mechanical Engineers, New York.

3. Development of a 3-D FBR fuel bundle-to-duct interaction analysis code marse;Itoh;SMiRT 11 C05/1,1991

4. Experimental fuel subassembly irradiation experience in EBR-2;Jackson,1979

5. K. Miki, Three-dimensional analysis for fuel pin deformations in an LMFBR assembly, 4th SMiRT D2/3.

Cited by 2 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. Full-scale finite element analysis of deformation and contact of a wire-wrapped fuel bundle subject to realistic thermal and irradiation conditions;Nuclear Engineering and Design;2020-08

2. Development of a Fast Breeder Reactor Fuel Bundle-Duct Interaction Analysis Code—BAMBOO: Analysis Model and Validation by the Out-of-Pile Compression Test;Nuclear Technology;2001-10

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