U-PuO2, U-PuC, U-PuN cermet fuel for fast reactor-Reference-Cited by-同舟云学术

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U-PuO2, U-PuC, U-PuN cermet fuel for fast reactor

Published:2018-02 Issue: Volume:499 Page:272-283
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Mishra Sudhir,Kaity Santu,Banerjee Joydipta,Nandi Chiranjeet,Dey G.K.,Khan K.B.

Funder

Bhabha Atomic Research Centre

Publisher

Elsevier BV

Subject

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

Reference41 articles.

1. A. A. Solomon, S.M. McDeavitt, Proceedings of ICONE10: Arlington, VA, April 14-18, 2002.

2. Core severe accidents with cermet fuels – a specific study for pressurized water reactors

3. Progress in core and cermet fuel modelling to calculate severe accidents

4. The feasibility of employing inert matrix ceramic fuels in a Russian light water reactor

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1. Thermal properties of HfN‐MoW surrogate cermet fuel for nuclear thermal propulsion;Journal of the American Ceramic Society;2022-11-16

2. N-Pu-U Ternary Phase Diagram Evaluation;MSI Eureka;2020-04-23

3. O-Pu-U Ternary Phase Diagram Evaluation;MSI Eureka;2020-04-23

4. The preparation and properties of the C-doped modified layers on uranium surfaces by pulsed laser irradiating;Journal of Nuclear Materials;2020-02

5. C-Pu-U Ternary Phase Diagram Evaluation;MSI Eureka;2019-11-12

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