Models for the release from fuel of Ce, La, Sr, and Eu in accident conditions-Reference-Cited by-同舟云学术

Models for the release from fuel of Ce, La, Sr, and Eu in accident conditions

Published:2011-01 Issue:1 Volume:53 Page:125-131
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Brillant G.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference36 articles.

1. Progress on ruthenium release and transport under air ingress conditions;Auvinen;Nucl. Eng. Design,2008

2. Barrachin, M., Jacq, F., 2002. Material data bank. Chemical equilibrium models. Tech. Rep. ASTEC-V1/DOC/01-14, IRSN-GRS.

3. Barrachin, M., Chevalier, P.Y., Cheynet, B., Fischer, E., 2006. A thermodynamic database for nuclear applications. In: MMSNF-5 Workshop, Nice, France.

4. Interpretation and modelling of fission product Ba and Mo releases from fuel;Brillant;J. Nucl. Mater.,2010

5. Ruthenium release from fuel in accident conditions;Brillant;Radiochim. Acta,2010

Cited by 11 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 the MAVR-TA code for analyzing the release and transport of fission products during a severe accident at a VVER NPP. Part 3 – Modelling of the release of fission products from the melt;Nuclear Engineering and Design;2023-12

2. Composition dependence of ferroelectric properties in (111)-oriented epitaxial HfO₂-CeO₂ solid solution films;Japanese Journal of Applied Physics;2022-08-02

3. Thermodynamic predictions of CANDU fuel volatilization and fission product behaviour under severe accident conditions;Journal of Nuclear Materials;2022-01

4. Development and validation of the MAVR-TA code for analyzing the release and transport of fission products during a severe accident at a nuclear power plant with VVER. Part 1 – Release of fission products from a fuel;Nuclear Engineering and Design;2021-12

5. Thermodynamically Informed Nuclear Fuel Codes—A Review and Perspectives;Thermo;2021-09-09