Crossmark

Thermohydraulic Calculation of the Design of an Irradiation Device for In-Reactor Tests of VVER-SCP Fuel Rod Models with Cores Based on Nuclear Fuel Swelling Simulators

Crossref DOI link: https://doi.org/10.1134/S1063778825100138

Published Online: 2026-03-04

Published Print: 2025-12

Update policy: https://doi.org/10.1007/springer_crossmark_policy

Authors

Izhutov, A. L.

Moiseev, V. S.

Kalinina, N. K.

Kaplina, M. S.

Moiseev, D. S.
License Information

Text and Data Mining valid from 2025-12-01

Version of Record valid from 2025-12-01
More Information

Article History

Received: 25 March 2025

Revised: 7 May 2025

Accepted: 20 May 2025

First Online: 4 March 2026

CONFLICT OF INTEREST

: The authors of this work declare that they have no conflicts of interest.

Document is current

Any future updates will be listed below