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

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

INTERACTION OF BORON CARBIDE WITH AUSTENITIC CHROMIUM-NICKEL STEELS

EDN: HLJGRV

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..

Abstract

The interaction of boron carbide, the most commonly used neutron absorber in nuclear reactors, with steels in relation to the operating conditions of fast neutron reactors, is considered. Austenitic chromium-nickel steel EI-847 (0X15N15MZB), which is corrosion-resistant in sodium, was used as the main structural material for absorbing elements of fast neutron reactors, and CHS-68 steel (KH16N15M2GTFR) is currently used.
Boron carbide does not interact with steel EI-847 in direct contact and in the presence of an air gap at 800 °C for 5000 hours. The mechanical properties of steel do not change significantly.
During compatibility tests of boron carbide in sodium, boron is dissolved and transferred to the shell to form complex boride phases such as (Cr, Ni, Mo)5B4 or (Cr, Ni, Mo)4B3. The mechanism of boron and carbon transfer through the sodium sublayer is considered, which is carried out due to chemical reactions of boron carbide with sodium oxides.
Irradiation reduces the temperature level of the beginning of the interaction of hot-pressed boron carbide (density (2.1–2.3)·103 kg/m3) with the shell of steel EI-847 compared to those obtained in bench conditions (500–550) °C to (100–120) °C. With an increase in the level of boron burnout, the intensity of interaction increases. When studying the PEL rods of the BN-600 reactor with a shell made of CHS-68 steel, with a service life of 502 effective days (12050 hours) at operating temperatures (390–520) °C and burn-up to 18.3·1027 capt/m3, no interaction of boron carbide with the shell was detected.

Keywords
boron carbide, austenitic steel, sodium, interaction, fast neutrons, microhardness, X-ray analysis, diffusion, burnout

Article Text (PDF, in Russian)

References

UDC 621.039.526: 621.039.534

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2026, no. 1, 1:14