Design features of water-cooled research reactors

Brief review of the design, specific features of thermal hydraulics of reactor cores and circulation loops of pool-type research reactors is given. Principal distinguishing features of research reactors as compared with industrial power reactor units are outlined. Design of reactor units is examined...

Full description

Bibliographic Details
Main Authors: I.A. Chusov, A.S. Shelegov, O.Yu. Kochnov
Format: Article
Language:English
Published: National Research Nuclear University (MEPhI) 2016-12-01
Series:Nuclear Energy and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S2452303816301182
id doaj-ea5e9b85f9cb44679925674f69a5f1ba
record_format Article
spelling doaj-ea5e9b85f9cb44679925674f69a5f1ba2020-11-25T01:11:02ZengNational Research Nuclear University (MEPhI)Nuclear Energy and Technology2452-30382016-12-012428729310.1016/j.nucet.2016.11.013Design features of water-cooled research reactorsI.A. Chusov0A.S. Shelegov1O.Yu. Kochnov2Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University “MEPhI”, 1 Studgorodok, Obninsk 249040, Kaluga region, RussiaObninsk Institute for Nuclear Power Engineering, National Research Nuclear University “MEPhI”, 1 Studgorodok, Obninsk 249040, Kaluga region, RussiaBranch of JSC “Karpov Institute of Physical Chemistry”, Kievskoe shosse 109km, Obninsk 249033, Kaluga region, RussiaBrief review of the design, specific features of thermal hydraulics of reactor cores and circulation loops of pool-type research reactors is given. Principal distinguishing features of research reactors as compared with industrial power reactor units are outlined. Design of reactor units is examined using the example of two research reactors VVR-M (Gatchina) and VVR-ts (Obninsk). Direction of coolant circulation constitutes the feature of research reactor installations which is of key importance. In contrast to power reactor units, propagation of coolant in research reactors is arranged in downwards direction, i.e. from core top to bottom. In connection with the above, particular design features of reactor support grids are discussed in the present study. A set of data is presented on the values of preset values of alarm and emergency protection triggering thresholds. The issue of modernization of the reactor core implemented by developing the family of fuel assemblies (FAs) of the new type is discussed separately using the example of modernization of the VVR-M reactor. It is demonstrated that by changing the FA design it is possible to significantly increase the neutron flux density and per unit power of reactor units. Tables containing main technical characteristics of different FAs for nuclear reactors of the IRT type are presented. Certain circuit engineering solutions for coolant circulation loops and characteristic design of research loops aimed at the solution of different research tasks are discussed.http://www.sciencedirect.com/science/article/pii/S2452303816301182Research reactorTurbulenceThermal hydraulicsHeat transfer in nuclear reactorFuel assemblyReactor safetyPool-type research reactorVVR-M2VVR-M3VVR-M5VVR-ts fuel assemblies
collection DOAJ
language English
format Article
sources DOAJ
author I.A. Chusov
A.S. Shelegov
O.Yu. Kochnov
spellingShingle I.A. Chusov
A.S. Shelegov
O.Yu. Kochnov
Design features of water-cooled research reactors
Nuclear Energy and Technology
Research reactor
Turbulence
Thermal hydraulics
Heat transfer in nuclear reactor
Fuel assembly
Reactor safety
Pool-type research reactor
VVR-M2
VVR-M3
VVR-M5
VVR-ts fuel assemblies
author_facet I.A. Chusov
A.S. Shelegov
O.Yu. Kochnov
author_sort I.A. Chusov
title Design features of water-cooled research reactors
title_short Design features of water-cooled research reactors
title_full Design features of water-cooled research reactors
title_fullStr Design features of water-cooled research reactors
title_full_unstemmed Design features of water-cooled research reactors
title_sort design features of water-cooled research reactors
publisher National Research Nuclear University (MEPhI)
series Nuclear Energy and Technology
issn 2452-3038
publishDate 2016-12-01
description Brief review of the design, specific features of thermal hydraulics of reactor cores and circulation loops of pool-type research reactors is given. Principal distinguishing features of research reactors as compared with industrial power reactor units are outlined. Design of reactor units is examined using the example of two research reactors VVR-M (Gatchina) and VVR-ts (Obninsk). Direction of coolant circulation constitutes the feature of research reactor installations which is of key importance. In contrast to power reactor units, propagation of coolant in research reactors is arranged in downwards direction, i.e. from core top to bottom. In connection with the above, particular design features of reactor support grids are discussed in the present study. A set of data is presented on the values of preset values of alarm and emergency protection triggering thresholds. The issue of modernization of the reactor core implemented by developing the family of fuel assemblies (FAs) of the new type is discussed separately using the example of modernization of the VVR-M reactor. It is demonstrated that by changing the FA design it is possible to significantly increase the neutron flux density and per unit power of reactor units. Tables containing main technical characteristics of different FAs for nuclear reactors of the IRT type are presented. Certain circuit engineering solutions for coolant circulation loops and characteristic design of research loops aimed at the solution of different research tasks are discussed.
topic Research reactor
Turbulence
Thermal hydraulics
Heat transfer in nuclear reactor
Fuel assembly
Reactor safety
Pool-type research reactor
VVR-M2
VVR-M3
VVR-M5
VVR-ts fuel assemblies
url http://www.sciencedirect.com/science/article/pii/S2452303816301182
work_keys_str_mv AT iachusov designfeaturesofwatercooledresearchreactors
AT asshelegov designfeaturesofwatercooledresearchreactors
AT oyukochnov designfeaturesofwatercooledresearchreactors
_version_ 1725173047667720192