Question

what is Design Considerations in VVER 1200 reactor ?

[Please submit the answer using text so I can just copy and paste it, thank you]

Answer 1

The design of AES-2006 of Generation 3+ with V-491 reactor plant is an evolutionary development of the designs with the VVER-1000 water cooled and water moderated reactor proved by a long-time operation. The AES-2006 design is based on the principle of safety assurance for the personnel, population and environment. The principle meets the requirements for the standards of radioactive substance releases into the environment and their content at normal operation, at anticipated operational occurrences including the design basis conditions (i.e. design events of Category 1-4) as well as at the beyond-design basis events during the entire service life of the nuclear power plant. One of the requirements during the reactor plant and process system design elaboration was not to reach the estimated value of a severe core damage 1.0E‑6 reactor/year and for the probability of emergency radioactivity release not to exceed 1.0E‑7 reactor/year. Level I and II PSA predict that these given values are not exceeded.

The following active systems are incorporated into the V-491 design:

High pressure emergency spray system;

Low pressure emergency spray system;

Emergency gas removal system;

Emergency boron injection system;

Emergency feedwater system;

Residual heat removal system;

Main steamline isolation system.

The following passive safety systems are incorporated into the V-491 design:

Emergency core cooling system, passive part;

System of passive heat removal from containment;

System of passive heat removal via steam generators;

Double-envelope containment and core catcher.

General plant data

Reactor thermal output 3200 MWth

Power plant output,gross 1170 MWe

Power plant output, net 1082 MWe

Power plant efficiency, net 33.9 %

Mode of operation Baseload and Load follow

Plant design life 60 Years

Plant availability target > 90 % Primary

coolant material Light Water

Secondary coolant material Light Water

Moderator material Light water

Thermodynamic cycle Rankine

Type of cycle Indirect

VVER-1200 (AES-2006) - THE BASIC DATA, FOR THE ST PETERSBURG AEP AND MOSCOW AEP VERSIONS ST PETERSBURG AEP MOSCOW AEP Service life (years) 60 Unit output, electric, low-sea-temp. site (MWe gross) 1198 1198 3212 3212 300 300 Reactor thermal output (MW) Heat supply capacity (MWL) Availability (%6) House load (including power for re-circulating cooling water supply) (%) >90 >90 7 6.83 Power plant efficiency (turbine in condensing mode) (9) 37.0 gross, 34 5 net 37.0 gross, 34.5 net Unplanned automatic scram per year Planned outage duration (annual) over seven years of operation (days, max) 4x 16, 2x 24, 4x 16, 2x 24 1 x 30 Duration of outage required every eight years to include turbine disas- sembly (days, max) 0.37 0.42 60 60 Number of operating personnel (person/MW) Design basis maximum fuel burn-up (average per fuel assembly) (MWd/kg) Fuel campaign duration lie fuel life in the core) (years) Refuelling frequency (months) 12(18) 298.2 12(18) 298.2 Primary coolant temp. at core inlet ("C) Primary coolant temp. at core outlet 328.9 328.9 86 000 Primary coolant flow rate through reactor vessel (m/hour) Primary coolant pressure at reactor vessel outlet (MPa) 86 000 16.2 16.2 Steam pressure at the steam generator outlet (MPa) 1602 1602 225 225 <0.2 Steam production rate per SG (t/hour) Feed water temperature at SG inlet (C) Steam moisture content at SG outlet (%) Total probability of core damage due to internal initiating events (per reactor year) Total probability of accidental sequences involving large releases caused by containment bypass or initial lack of leak tightness <0.2 <7.37 x 10 < 4.16x 10" <3.71 x 10 <1.77 x 10"

ST PETERSBURG AEP MOSCOW AEP DOUBLE CONTAINMENT DIMENSION 50.8 EXTERNAL, PROTECTIVE, CONTAINMENT (REINFORCED CONCRETE): Internal diameter (m) 50 Height of dome (m) Thickness (cylindrical section) (m) 2.2 71.4 Thickness (dome part) (m) 0.8 INTERNAL, HERMETIC, CONTAINMENT (ALSO REINFORCED CONCRETE): Internal diameter (m) 67.1 Height of the dome (m) Thickness (cylindrical section) (m) 1.2 Thickness (dome part) (m) 1.1 1.2

link to a file that could be useful.(you can use copy paste feature from all this pdfs )

https://www.rosatom.ru/upload/iblock/0be/0be1220af25741375138ecd1afb18743.pdf

https://aris.iaea.org/PDF/VVER-1200(V-491).pdf

https://www.sciencedirect.com/science/article/pii/S245230381730095X

https://www.oecd-nea.org/mdep/events/conf-2017/presentations/s4/6.%20SVETLOV%20Sergey_%20Atomproekt_Presentation%20Svetlov_ENG-ver3.pdf