Release behavior of radionuclides from MOX fuels irradiated in a fast reactor during heating tests-Reference-Cited by-同舟云学术

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Release behavior of radionuclides from MOX fuels irradiated in a fast reactor during heating tests

Published:2020-08 Issue: Volume:536 Page:152199
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Tanaka K.,Sato I.,Onishi T.,Ishikawa T.,Hirosawa T.,Katsuyama K.,Seino H.,Ohno S.,Hamada H.,Tokoro D.,Sekioka K.,Suto M.

Publisher

Elsevier BV

Subject

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

Reference21 articles.

1. United States Nuclear Regulatory, NUREG-0772, 1981.

2. NUREG/CR-6264;Lorenz,1995

3. Overview of experimental programs on core melt progression and fission product release behaviour

4. Fission products and nuclear fuel behaviour under severe accident conditions part 1: Main lessons learnt from the first VERDON test

5. Fission products and nuclear fuel behaviour under severe accident conditions part 2: Fuel behaviour in the VERDON-1 sample

Cited by 1 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. Experimental reactor Joyo;Sodium-cooled Fast Reactors;2022

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