Preview

Vestnik natsional'nogo issledovatel'skogo yadernogo universiteta "MIFI"

Advanced search

INFORMATION SUPPORT SYSTEM FOR REACTOR INSTALLATIONS DECOMMISSIONED

https://doi.org/10.26583/vestnik.2025.2.8

EDN: OHPPHW

Abstract

The article discusses the principles of building an information support system for decommissioned reactors, using the example of a nuclear power plant with an RBMK-1000 reactor. The article describes approaches to building the structure of algorithms for such a system, and discusses security functions that are important for their implementation, to be taken into account when building an information support system. The authors studied the neutron and technological parameters that allow monitoring and emergency protection of the reactor until the fuel is completely discharged from the reactor core, which has been shut down for decommissioning. Special attention in the article is paid to the fact that the information support system must comply with all the norms and rules applicable to systems operating at power units. The data obtained make it possible to develop a uniform approach, in the form of an information support system, which allows monitoring and protecting the reactor using fewer equipment compared to standard systems operating at power units that are operated in the power generation mode.

About the Authors

G. V. Kolibas
National research nuclear University «MEPhI»
Russian Federation


A. O. Tolokonskiy
National research nuclear University «MEPhI»
Russian Federation


References

1. Abramov M.I., Avdeev V.I., Adamov E.O. e.a. Kanal'nyj yadernyj reaktor / pod obshchej redakciej Yu.M. Cherkashova [Ducted nuclear reactor. Under the general editorship of Yu.M. Cherkashov]. Moscow, GUP NIKIET Publ., 2006. pp. 86-165.

2. Andryushechko S.A., Vasiliev B.Yu. VVER-1200: evolyuciya klassiki [VVER-1200: evolution of classics]. Moscow, Logos Publ., 2019, 672 p.

3. Morozov A.V., Sakhipgareev A.R. Eksperimental'naya ocenka vliyaniya kontaktnoj kondensacii parogazovoj smesi na rabotu passivnyh sistem bezopasnosti VVER [Experimental assessment of the effect of contact condensation of a combined-cycle gas mixture on the operation of passive VVER safety systems]. Izvestiya vysshih uchebnyh zavedenij. Yadernaya energetika, 2017. no.1. pp. 17-28. (in Russian)

4. Asmolov V.G., Blinkov V.N., Povarov V.P., Chernikov O.G. Osnovy obespecheniya bezopasnosti AES: uchebnoe posobie dlya studentov vuzov [Fundamentals of NPP safety: a textbook for university students]. Moscow, NIYaU MIFI Publ., 2025. 296 p.

5. Kulakov A.V., Mikhailov M.N. Sovremennye upravlyayushchie sistemy dlya ob"ektov povyshennoj tekhnogennoj opasnosti na primere atomnoj energetiki: opyt sozdaniya i perspektivy primeneniya [Modern control systems for facilities of increased technogenic hazards on the example of nuclear energy: creation experience and application prospects]. Izvestiya Rossijskoj Akademii nauk. Energetika, 2013. no. 1, pp. 107-115. (in Russian)

6. Filipchuk E.V., Potapenko P.T., Postnikov V.V. Upravlenie nejtronnom polem yadernogo reaktora [Control of the neutron field of a nuclear reactor]. Moscow, ENERGOIZDAT Publ., 1981 . 280 p.


Review

For citations:


Kolibas G.V., Tolokonskiy A.O. INFORMATION SUPPORT SYSTEM FOR REACTOR INSTALLATIONS DECOMMISSIONED. Vestnik natsional'nogo issledovatel'skogo yadernogo universiteta "MIFI". 2025;14(2):163-172. (In Russ.) https://doi.org/10.26583/vestnik.2025.2.8. EDN: OHPPHW

Views: 64


Creative Commons License
This work is licensed under a Creative Commons Attribution 4.0 License.


ISSN 2304-487X (Print)