Study of thermodynamic properties of U1-yPuyO2 MOX fuel using classical molecular Monte Carlo simulations-Reference-Cited by-同舟云学术

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Study of thermodynamic properties of U1-yPuyO2 MOX fuel using classical molecular Monte Carlo simulations

Published:2020-06 Issue: Volume:534 Page:152125
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Takoukam-Takoundjou Cyrille,Bourasseau Emeric,Lachet Véronique

Funder

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference99 articles.

1. A review of the thermophysical properties of MOX and UO2 fuels;Carbajo;J. Nucl. Mater.,2001

2. Thermophysical properties of uranium dioxide;Fink;J. Nucl. Mater.,1981

3. Diffuse transition and melting in fluorite and antifluorite type of compounds. Heat content of potassium sulfide from 298 to 1260.degree.K;Dworkin;J. Phys. Chem.,1968

4. Analysis of recent measurements of the heat capacity of uranium dioxide;Ronchi;J. Alloys Compd.,1994

5. Faraday's Diary;Faraday,1932

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