Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

Vereshchagina T.N., Loginov N.I.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Vereshchagina T.N. – Chief Researcher, Dr. Sci.(Tech.), A.I. Leypunsky Institute for Physics and Power Engineering.
Loginov N.I. – Chief Researcher, Dr. Sci.(Tech.), A.I. Leypunsky Institute for Physics and Power Engineering. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7(484) 399-85-55; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..


It is supposed using of liquid lithium both to generate tritium and to cool simultaneously blankets of fusion reactors ITER and DEMO. It is known that additional hydraulic resistance take place when conductive liquids are pumping throw magnetic field, so pumping power must be increased. This additional hydraulic resistance is proportional to conductivity of liquid. Thus, eutectic lead-lithium alloy with four time less conductivity in comparison of lithium is considered as alternative. The purpose of the paper is comparative analysis of magnetohydrodynamic pressure drop at a flow of those two liquid metals throw magnetic field. The comparison is carried out by calculation using known mathematic formula for the hydraulic resistance coefficient in the flow of conductive liquid throw the circular conductive pipe placed in a transvers magnetic field. It is considered that the blanket heat power, which is necessary to remove, for both liquid metals is the same. As a result of the calculation it was shown that the hydraulic resistance coefficient for lead-lithium alloy is significantly less than for lithium. However, pressure drop occurs for both cases practically equal, because of lead-lithium alloy density is higher than lithium one, and its heat capacity is less. Therefore, exchange of lithium for lead-lithium alloy das not reduces pumping power.

coolant, lithium, lead-lithium alloy, blanket, ITER, magnetic field, hydrodynamic resistance, hydraulic losses, electrical conductivity

Article Text (PDF, in Russian)


UDC 621.039.6

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2018, issue 3, 3:7