Inert matrix fuel behaviour in test irradiations-Reference-Cited by-同舟云学术

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Inert matrix fuel behaviour in test irradiations

Published:2006-06 Issue:1-3 Volume:352 Page:291-299
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Hellwig Ch.,Streit M.,Blair P.,Tverberg T.,Klaassen F.C.,Schram R.P.C.,Vettraino F.,Yamashita T.

Publisher

Elsevier BV

Subject

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

Reference34 articles.

1. Inert matrix fuel strategies in the nuclear fuel cycle: the status of the initiative efforts at the 8th Inert Matrix Fuel Workshop

2. Comparison of Pressurized Water Reactor Core Characteristics for 100% Plutonium-Containing Loadings

3. Erbium: alternative poison? Stabilisation additive? What future?

4. Conceptual studies for pressurised water reactor cores employing plutonium–erbium–zirconium oxide inert matrix fuel assemblies

5. Validation efforts for the neutronics of a plutonium–erbium–zirconium oxide inert matrix light water reactor fuel

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1. Order-disorder structural transition and thermal expansion properties in Ce-substituted Y2Zr2O7 system;Journal of Nuclear Materials;2024-11

2. Phase evolution in M1-xPuxO2 (0.0 ≤ x ≤ 0.6) (M = Zr, Th) as potential inert matrix fuel system under reducing and oxidizing conditions;Journal of Nuclear Materials;2021-04

3. Composite Fuel (Cermet, Cercer);Comprehensive Nuclear Materials;2020

4. Thermal conductivity of Mo-reinforced ZrO2 composites fabricated by spark plasma sintering for inert matrix fuels;Materials & Design;2017-11

5. Fabrication of ZrO2-based nanocomposites for transuranic element-burning inert matrix fuel;Nuclear Engineering and Technology;2015-08

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