Journal Article

IMPULSE-2025-00143

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png Evaluation of tungsten as diffusion barrier for high-density U-Mo fuel using heavy-ion irradiation

Schwarz, C. (Corresponding author)MLZ* ; Shi, J.MLZ* ; Oberbauer, A.MLZ* ; Stepnik, B. ; Petry, W.MLZ*

2026
Elsevier Science Amsterdam [u.a.]

Please use a persistent id in citations: doi:10.1016/j.jnucmat.2025.156210

Abstract: Monolithic plate-type nuclear fuels for research reactors based on a U-Mo alloy require a coating barrier between the fuel zone and the Al-based cladding to suppress the growth of the undesired interaction layer. The effectiveness of tungsten - an alternative to the commonly used zirconium - is studied to this end. Physical vapor deposition (PVD) serves as a suitable method to produce the required barrier layers. These W coatings turn out brittle, especially when combined with a subsequent cladding application, but show promising behavior in limiting thermal diffusion. This is confirmed in heavy-ion irradiation experiments to simulate in-pile performance of the fuel system. Irradiation of the W barrier from the direction of the Al cladding as well as from the U-Mo side displays mainly interaction of W and Al. As observed, a layer of 1 µm W is sufficient to prevent interaction of U-Mo and Al up to fission density equivalents of 7.5·10^20 fissions/cm³. The temperature effect dominates the growth of interaction layer when the sample temperature is increased from 140 °C to 200 °C.

Keyword(s): Engineering, Industrial Materials and Processing (1st) ; Materials Science (2nd)

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Contributing Institute(s):

1. CNSI-EXPERIMENT (CNSI-EXPERIMENT)

Experiment(s):

1. HEU-MEU: Brennstoffentwicklung

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Database coverage:
; Clarivate Analytics Master Journal List ; Current Contents - Engineering, Computing and Technology ; Current Contents - Physical, Chemical and Earth Sciences ; Ebsco Academic Search ; Essential Science Indicators ; IF < 5 ; JCR ; Nationallizenz ; SCOPUS ; Science Citation Index Expanded ; Web of Science Core Collection

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