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

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

THE EXPERIENCE OF POST-RADIATION STUDIES OF THE CONTROL RODS OF THE BN-350 AND BN-600 REACTORS

EDN: XJYLHH

Authors & Affiliations

Tarasikov V.P.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Tarasikov V.P. – Leading Researcher, Cand. Sci. (Tech.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, 249033. Tel.: +7 (484) 399-70-00 (add 82-04); e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it., This email address is being protected from spambots. You need JavaScript enabled to view it..

Abstract

In the process of developing and justifying the regulatory bodies of fast reactors, primarily the BN-350 and BN-600 reactors and the BN-800 reactor project, extensive research was conducted in the field of physics, technology and materials science. Many technical solutions and ideas were considered and tested. For these purposes, the construction of the second stage of “the hot laboratory” was completed at IPPE in 1970. Along with the hot chambers, a line of heavy boxes was built, intended for the development of work in the IPPE to justify the use of absorbing materials from the organs of fast reactors and, first of all, the BN-350 under construction at that time. The line of heavy protective boxes was equipped with both traditional equipment (a cutting machine, a device for measuring geometry, sample density, metallographic equipment), as well as new installations and methods for studying irradiated absorbing materials were developed. Special equipment: installation for determining the amount of helium and tritium in irradiated boron-containing materials, high-temperature furnaces and a dilatometer. Based on many years of research, empirical dependences were obtained on the effect of the degree of burnout and temperature on the volume changes of the absorber most acceptable for the fast neutron spectrum – boron carbide. The structure, thermophysical properties and accumulation zones in boron carbide during irradiation and its compatibility with structural materials have been studied. The purpose of this work is a summary of the results of materials science post-reactor studies of control rods, the transfer of experience and the use of research results in the modernization of the rod design. The stages of modernization of the design of the control rods are considered.

Keywords
absorbing element, boron carbide, irradiation, swelling, gas accumulation, thermal conductivity, burnout, cracking mechanisms, compatibility, modernization

Article Text (PDF, in Russian)

References

UDC 621.039.526: 621.039.534

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 2, 2:13