Development and Validation of ALFUS: An Irradiation Behavior Analysis Code for Metallic Fast Reactor Fuels-Reference-Cited by-同舟云学术

Development and Validation of ALFUS: An Irradiation Behavior Analysis Code for Metallic Fast Reactor Fuels

Published:1999-10 Issue:1 Volume:128 Page:113-123
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Ogata Takanari¹,Yokoo Takeshi²

Affiliation:

1. Central Research Institute of Electric Power Industry Nuclear Fuel Cycle Department, 2-11-1 Iwato-kita, Komae-shi, Tokyo 201-85111, Japan

2. Central Research Institute of Electric Power Industry Nuclear Systems Department, 2-11-1 Iwato-kita, Komae-shi, Tokyo 201-85111, Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT99-A3018

Reference16 articles.

1. Analytical study on deformation and fission gas behavior of metallic fast reactor fuel

2. Swelling behavior of U-Pu-Zr fuel

3. T. NAKAJIMA, M. ICHIKAWA, Y. IWANO, K. ITO, H. SAITO, K. KASHIMA, M. KINOSHITA, and T. OKUBO, “FEMAXI-III: A Computer Code for the Analysis of Thermal and Mechanical Behavior of Fuel Rods,” JAERI-1298, Japan Atomic Energy Research Institute (Dec. 1985).

4. Constituent Migration Model for U-Pu-Zr Metallic Fast Reactor Fuel

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