Research and validation on the numerical algorithm of mechanical module in a transient fuel rod performance code for fast reactor-Reference-Cited by-同舟云学术

Research and validation on the numerical algorithm of mechanical module in a transient fuel rod performance code for fast reactor

Published:2022-06 Issue: Volume:171 Page:108991
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Yang Guangliang,Guo Zixuan,Wang Peng,Wang Weixiang,Liao Hailong,Ding Tao,Chen Hongli

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference15 articles.

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4. Agosti, F., Botazzoli, P., Di Marcello, Valentino, Pastore, Giovanni, Luzzi, Lelio., 2009. Extension of the TRANSURANUS Code to the Analysis of Cladding Materials for Liquid Metal Cooled Fast Reactors: a Preliminary Approach. Politecnico di Milano, Technical Report, CESNEF-IN-11-2009.

5. Yacout, A. M., and M. C. Billone. “Current Status of the LIFE Fast Reactors Fuel Performance Codes.” (2013). https://inis.iaea.org/search/search.aspx?orig_q=RN:45089626

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1. Study on the Steady-State Performance of the Fuel Rod in M2LFR-1000 Using KMC-Fueltra;Springer Proceedings in Physics;2023

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