Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Basic safety principles of KLT-40C reactor plants

Beliaev, V.; Polunichev, V. (OKB Mechanical Engineering, Nizhny Novgorod (Russian Federation))

Abstract

The KLT-40 NSSS has been developed for a floating power block of a nuclear heat and power station on the basis of ice-breaker-type NSSS with application of shipbuilding technologies. Basic reactor plant components are pressured water reactor, once-through coil-type steam generator, primary coolant pump, emergency protection rod drive mechanisms of compensate group-electromechanical type. Basic RP components are incorporated in a compact steam generating block which is arranged within metal-water shielding tank’s caissons. Domestic regulatory documents on safety were used for the NSSS design. IAEA recommendations were also taken into account. Implementation of basic safety principles adopted presently for nuclear power allowed application of the KLT40C plant for a floating power unit of a nuclear co-generation station.

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key words: cogeneration; control rod drives; dual-purpose power plants; licensing regulations; primary coolant circuits; reactor safety; scram rods; shielding; ship propulsion reactors; steam generation; steam generators
Reference:
Advisory group meeting on small power and heat generation systems on the basis of propulsion and innovative reactor technologies. Obninsk (Russian Federation) 20-24 Jul 1998
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1172, pp:35-45