Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

Fadeev Yu.P., Bolshukhin M.A., Pakhomov A.N., Khizbullin A.M., Sokolov A.N., Shmelev D.I.
JSC "Afrikantov OKB Mechanical Engineering", Nizhny Novgorod, Russia

Khizbullin A.M. –Deputy Head of Department, Cand. Sci. (Tech.), JSC "Afrikantov OKB Mechanical Engineering". Contacts: 15, Burnakovsky proyezd, Nizhny Novgorod, Russia, 603074. Tel: (831)275-25-71; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it.
Fadeev Yu.P. - Chief Designer, JSC "Afrikantov OKB Mechanical Engineering".
Bolshukhin M.A. – Head of Division, Cand. Sci. (Tech.), JSC "Afrikantov OKB Mechanical Engineering".
Pakhomov A.N. –Head of Department, JSC "Afrikantov OKB Mechanical Engineering".
Sokolov A.N. – Head of Design Group, JSC "Afrikantov OKB Mechanical Engineering".
Shmelev D.I. – Design Engineer, JSC "Afrikantov OKB Mechanical Engineering".


Enhancing the nuclear safety of transportable reactor plants is one of the major aspects of their de-velopment. At the same time, the priority is placed on introducing passive systems that do not require power supply and personnel’s actions for their normal operation. This is especially important for floating power units located in the regions remote from the centralized power supply where such units may be the only sources of electricity and heat.

This paper describes a proposed passive emergency heat removal system for advanced transportable reactor plants and also provides computational analysis results for system operation in a plant black-out accident both in the case with a pressurized primary circuit and in the case of a LOCA such that no control actions are taken by the operating personnel.

The computational analysis has shown that the proposed option of the passive emergency heat removal system ensures that the accident progresses without exceeding the design limits for pressure in the pressurized primary circuit, without any time limits and without any actions taken to manage the accident process — and the same is for the containment with a non-cooled volume in the case of a LOCA. The capabilities of the proposed system allow it to operate in an active mode, which, in its turn, allows the normal and emergency operation functions to be joined in one system.

The application of the proposed passive emergency heat removal system in the advanced transportable reactor plants will allow both safety and competitiveness of these plants to be enhanced in the future.

Nuclear safety, transportable reactor plants, marine reactor plants, passive safety systems, loss-of-heat-removal accidents, LOCA, Complex of Safety Systems, emergency heat removed system, source of electric energy, source of heat energy

Article Text (PDF, in Russian)


UDC 612.039.58

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2016, issue 3, 3:6