EXPERIENCE OF USE OF LEAD-BISMUTH COOLED REACTORS IN NUCLEAR SUBMARINES. PROSPECTS FOR USE OF LEAD-BISMUTH COOLANT IN CIVIL NUCLEAR POWER

Authors & Affiliations

Toshinsky G.I.^1,2

¹A.I. Leypunsky Institute for Physics and Power, Obninsk, Russia
²JSC “AKME-engineering”, Obninsk, Russia

Abstract

Design of SVBR-100 fast reactor now under development is based on the experience gained in designing and operating nuclear submarine (NS) reactors cooled by lead-bismuth. The paper presents the history of development of this unique nuclear power area, experience gained in operating leadbismuth cooled NS reactors and the main problems that were solved in the course of mastering this technology, in particular, radiation safety issues concerning operation of the equipment contaminated by polonium-210. As applied to the civilian reactors, analysis of NPP severe accidents occurred during recent decades was made. A conclusion was made about the strong influence of potential energy accumulated by the coolant on NPP safety and economical characteristics. The main conceptual characteristics of multi-purpose modular reactor SVBR-100 with lead-bismuth coolant having min amount of accumulated potential energy are considered, as well as possible areas of application of such reactors.

Keywords
nuclear submarine, lead-bismuth coolant, technology, radiation safety, polonium-210, coolant potential energy, civil nuclear power, SVBR-100 fast reactor, modular design

Article Text (PDF)

UDC 621.039.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2015, issue 4, 4:12