Journal Article

IMPULSE-2023-00243

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png Hydrogen diffusion in Zr-2.5Nb pressure tubes specimens between 300°C-400°C by in-situ neutron imaging experiments

Stella, V. M. (Corresponding author) ; Soria, S. R. ; Gomez, A. ; Grosse, M. ; Schulz, M.MLZ* ; Santisteban, J. R.

2023
IOP Publ. Bristol

Please use a persistent id in citations: doi:10.1088/1742-6596/2605/1/012037

Abstract: Zirconium (Zr) alloys are widely used in nuclear power plants as fuel cladding and are susceptible to hydrogen (H) degradation. For long operational service, Zr-based components can suffer a mechanism known as Delayed Hydride Cracking (DHC) associated to an increase of the crack propagation velocity by the re-orientation and precipitation of Zr hydride. In this process, the H mobility has a great influence. In the present work, the isothermal diffusion of H in Zr-2.5%Nb specimens obtained from a CANDU pressure tube were studied at consecutive temperatures of 300°C, 350°C, 375°C and 400°C. H content and mobility were quantified by in-situ neutron imaging experiments performed on ANTARES, the cold neutron imaging facility of FRM II. The time evolution of the H concentration across the specimen allowed the determination of diffusion coefficients, and an assessment of the limitations of existing models commonly used to describe H diffusion.

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

---

Contributing Institute(s):

1. ANTARES (ANTARES)
2. MATSCI (MATSCI)
3. METHODS (METHODS)

Experiment(s):

1. ANTARES: Cold neutron radiography and tomography station (SR4a)

Appears in the scientific report 2023

---

Database coverage:
; Nationallizenz

---