Water cooled and moderated natural circulation boiling water reactor (VK-300)
Creators
Description
The VK-300 is a 250 MW(e) simplified water cooled and water moderated boiling water reactor with natural circulation of coolant and passive systems. The major technological principles of the concept are: the simplicity in design resulting from a single circuit scheme and natural circulation of coolant in the core; the use of water as a coolant and moderator the production of steam of required parameters directly in the reactor due to an integral arrangement; and strong reliance on passive features and systems to achieve a high level of safety. The VK-300 is a direct successor of the VK-50, - one of the simplified boiling water reactors developed in Russia The VK-50 has been successfully operated for decades at the Research Institute for Nuclear Reactors (RIAR) in Dimitrovgrad, the Russian Federation. In 2001, the design of the VK-300 of 750 MW(th), 250 MW(e) was developed to supply electricity and heat of up to 400 GCal/h within a nuclear co-generation plant to be built at the Krasnoyarsk Mining and Chemical Combine. This design was developed by Russian research and design organizations: the Research and Development Institute of Power Engineering (RDIPE) named after N.A. Dollezhal and also known as NIKIET, the Russian Research Centre 'Kurchatov Institute', and the Institute of Physics and Power Engineering (Obninsk), also involving the RIAR, VNIINM, VNIIPIET, VNIIPIPT and others. During project development, maximum use was made of the experience in design, production and operation of the following equipment used in the following operating reactors: VVER-1000 - reactor vessel, cap, internals, fuel assemblies, fuel elements, steam separators, structural materials; RBMK - in core power detectors, pulse current fission chambers, analogue level gauges and level indicators; VK-50 - core cooling by natural circulation of boiling water coolant; SM.3, IVV.10 research reactors - control and protection system (CPS) actuator drives. Several options were considered in the core arrangement and reactor design at the developmental stage of the VK-300 project to enhance safety and economic efficiency. Specifically, of all options considered the principle of passive operation of main safety systems was retained to achieve an optimum balance between the enhanced safety and improved economic characteristics. As of 2004, the project documentation on the VK-300 was developed for a four-unit nuclear cogeneration plant to be built in the Arkhangelsk region of the Russian Federation
Additional details
Identifiers
Publishing Information
- ISBN
- 92-0-101006-0
- Imprint Title
- Status of innovative small and medium sized reactor designs 2005. Reactors with conventional refuelling schemes
- Imprint Pagination
- 712 p.
- Journal Page Range
- p. 287-310
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1485
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37052834
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COGENERATION; COOLANTS; DESIGN; DUAL-PURPOSE POWER PLANTS; FISSION CHAMBERS; FUEL ASSEMBLIES; FUEL ELEMENTS; HEAT; LEVEL INDICATORS; NATURAL CONVECTION; REACTOR OPERATION; REACTOR SAFETY; REACTOR VESSELS; RESEARCH REACTORS; RUSSIAN FEDERATION; STEAM SEPARATORS; WWER TYPE REACTORS
- Descriptors DEC
- CONTAINERS; CONVECTION; EASTERN EUROPE; ENERGY; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; EUROPE; HEAT TRANSFER; IONIZATION CHAMBERS; MASS TRANSFER; MEASURING INSTRUMENTS; NEUTRON DETECTORS; OPERATION; POWER GENERATION; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; RADIATION DETECTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SEPARATION EQUIPMENT; STEAM GENERATION; THERMAL REACTORS; VAPOR SEPARATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs, 12 figs, 13 tabs