PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

THERMOMECHANICAL INTERACTION OF FUEL ASSEMBLY COMPONENTS IN THE CORE OF BN-TYPE REACTORS UNDER HIGH-DOSE IRRADIATION

EDN: MZIDJV

Authors & Affiliations

Vilensky O.Yu., Lapshin D.A., Ryabtsov A.V., Farakshin M.R.
Afrikantov Experimental Design Bureau for Mechanical Engineering, Nizhny Novgorod, Russia

Vilensky O.Yu. – Head of Department, Cand. Sci. (Tech.). Contacts: 15, Burnakovsky proyezd, Niznny Novgorod, Russia, 603074. Tel.: +7 (831) 246-97-21; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Lapshin D.A. – Head of Department, Cand. Sci. (Tech.).
Ryabtsov A.V. – Deputy Head of Department, Cand. Sci. (Tech.).
Farakshin M.R. – Head of Department, Cand. Sci. (Tech.).

Abstract

The paper presents the main results from the analysis of the thermomechanical interaction between the bundle of fuel elements and the hexagonal cover of the fuel assembly under high-dose irradiation for the most conservative case when radiationally swelled fuel elements and wire impact on the hexagonal cover.
The authors identified and evaluated the nature and values of voltage distribution irregularities caused by the local interaction of the hexagonal cover with the spacer wire and the spacer wire with the cladding of fuel elements.
To solve the problem of thermomechanical interaction of a bundle of fuel elements with a hexagonal cover of a fuel assembly, the ANSYS software package certified by Rostechnadzor authorities was supplemented with developed user units for accounting for the effects of radiation swelling and radiation creep of structural materials.
The authors assessed the operability of the fuel assembly components in the core according to the strength criteria.
The obtained results indicate the need to take into account the stresses caused by the local interaction of the hexagonal cover with the spacer wire and the spacer wire with the cladding of fuel elements under high-dose irradiation.

Keywords
fuel assembly, fuel element, spacer wire, thermomechanical interaction, radiation swelling, radiation creep

Article Text (PDF, in Russian)

References

UDC 539.3

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 4, 1:10