Simulation of radioactive fission gas release from defective PWR fuel rod using the MFPR/R mechanistic code-Reference-Cited by-同舟云学术

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Simulation of radioactive fission gas release from defective PWR fuel rod using the MFPR/R mechanistic code

Published:2023-09 Issue: Volume:583 Page:154536
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Tarasov V.I.,Ozrin V.D.,Veshchunov M.S.

Funder

International Atomic Energy Agency

Publisher

Elsevier BV

Subject

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

Reference38 articles.

1. A generalized model for fission-product transport in the fuel-to-cladding gap of defective fuel elements;Lewis;J. Nucl. Mater.,1990

2. Fuel performance and fission product release studies for defected fuel elements;Lewis;Nucl. Technol.,1993

3. Mechanisms of fission gas release from defective fuel rods to water coolant during steady-state operation of nuclear power reactors;Veshchunov;Nucl. Eng. Des.,2019

4. Development of the mechanistic code MFPR for modelling fission products release from irradiated UO2 fuel;Veshchunov;Nucl. Eng. Des.,2006

5. Mechanistic modelling of urania fuel evolution and fission product migration during irradiation and heating;Veshchunov;J. Nucl. Mater.,2007

Cited by 3 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. Chromia-doped UO2 fuel: An engineering model for chromium solubility and fission gas diffusivity;Journal of Nuclear Materials;2024-12

2. Modelling of defective CANDU fuel phenomena;Journal of Nuclear Materials;2024-03

3. Chromia-Doped Uo2 Fuel: An Engineering Model for Chromium Solubility and Fission Gas Diffusivity;2024

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