BELENE NPP Reactor plant V-466B

BELENE NPP BELENE NPP Reactor plant Reactor plant

V-466BV-466B

FSUE OKB «GIDROPRESS» Ryzhov S.B., Ermakov D.N., Repin A.I.

May, 2008

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FSUE OKB "GIDROPRESS"FSUE OKB "GIDROPRESS" Federal State Unitary Enterprise, Experimental

and Design organization “Gidropress”, as the General design organization for reactor plants, is engaged in development of designs of equipment and systems, intended for power engineering and nuclear engineering for more than half a century.

Using projects, developed by OKB “Gidropress” more 85 reactor plants of different types have been constructed.

Our designs have been implemented at the nuclear power facilities in Russia, Bulgaria, Ukraine, Czech Republic, Finland, Germany, Hungary, Slovakia, Armenia, China, India.

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Advanced reactor plant VVER-Advanced reactor plant VVER-1000(1000(V-466BV-466B ))Since the moment of RP V-320 development the

successful progress has been made for the concept of RP VVER-1000. There were developed the designs of RP V-392 for A-92 NPP(of improved safety), RP V-428 (in operation in China), RP V-412 (under implementation in India). A number of design improvements have been made in the above-mentioned projects concerning equipment and systems that facilitated reaching the safety level that meets the up-to-date NEC and international requirements and IAEA recommendations

In 2004-2006 there was performed an assessment of AES-92 project concerning EUR requirements of revision С. Assessments were performed by western experts with participation of project designers. As a result of this work a good conformity of the project with the specified requirements was determined

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Basic Changes in the DesignBasic Changes in the Design (1) advanced reactor (service life-60 years) . up-to-date fuel cycle on the basis of usage of fuel

assemblies (FA-A or FA-2) with uranium-gadolinium fuel of latest modifications providing high fuel burnup;

application of new SGs (service life-up to 60 years) application of new Reactor coolant pumps application of new CPS drives ShEM-3 implementation of additional passive safety

systems corium localization device (core-catcher) and

changes in arrangement of the reactor pit equipment and in design of some of its components

Design RP main equipment service life - 60 years

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Basic Changes in the DesignBasic Changes in the Design (2) application of up-to-date digital I&C (including

latest modifications of Monitoring Control and Diagnostic System (MCDS), neutron flux monitoring equipment (NFME), Control and Protection System (CPS), emergency level gauge);

implementation of PRZ PORV control procedure under beyond design basis accidents (implementation of feed and bleed procedure);

using of up-to-date automatic systems for RP main equipment inspection;

justification of “leak-before-break” concept for the main RP pipelines and application of the required leak detection systems;

usage of removable modular thermal insulation;

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Basic Changes in the DesignBasic Changes in the Design (3) implementation of up-to-date surveillance

programme with placing the surveillance specimens on the reactor vessel;

extension of the operation period of RP main equipment between technical inspections

using of fuel handling machine with the increased rates of FA horizontal and vertical motion;

using of sipping method in performing check of leak tightness of fuel rod claddings with keeping the traditional method of leak check of claddings

using the reactor main joint power nut driver with simultaneous elongation of all studs, as well as of nut drivers for detachable joints of steam generators, pressurizer, ECCS accumulators

;;

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Arrangement of Reactor in Concrete Arrangement of Reactor in Concrete PitPit

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Advanced ReactorAdvanced Reactor

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Advanced ReactorAdvanced ReactorThe improvements include: lengthening the advanced reactor vessel by 300

mm at the expense of lengthening the supporting shell;

increase in the number of CPS CRs; increase of diameter of reactor vessel; using the CPS drive ShEM-3; completely new surveillance programme

(arrangement of the irradiated surveillance specimens directly on RPV wall

limitation of nickel content in welds and of harmful impurities in base metal and welds

reducing Тко of nozzles zone shells to minus 35оС

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CPS drive ShEM-3CPS drive ShEM-3

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CPS drive ShEM-3CPS drive ShEM-3 power electromagnetic system is optimized and

dynamic drive characteristic is improved under motion conditions

drive service life (mechanical part) is extended up to 40 years whereas the prototype mechanical part has a service life of 20 years, service life of electromagnets – 10 years and that of position indicator – 5 years

pulling force is increased ( twice as much) PPI is used with indication of pitch position each

20 mm of extension shaft motion (LPI in ShEM drive provides indication of position of extension shaft with 350 mm pitch)

One drive seal (instead of two in prototipe design)

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Steam generator Steam generator ((spaced corridor arrangement of spaced corridor arrangement of

tubes)tubes)

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Steam generator Steam generator ((spaced corridor arrangement of spaced corridor arrangement of

tubes) tubes) increase circulation rate in the tube bundle that will reduce probability of damage of heat exchanging tubes due to decrease in the growth rate of deposits on the heat exchanging tubes and degree of concentration of corrosion-active impurities under them

reduce possibility of clogging the intertube space with spalled sludge

make easy access into intertube space for inspection of heat exchanging tubes and their cleaning in necessity

increase water inventory in steam generator enlarge the space under the tube bundle for easy

removal of the sludge Drop of Coolant headers stress; Improvement of SG heat exchanging tubes

manufacturability and maintainability

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Reactor Coolant Pump SetReactor Coolant Pump Set

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Reactor Coolant Pump SetReactor Coolant Pump Set

main thrust bearing with water cooling and lubricant

double-speed electric motor, that reduces loads to transformer during startup (this provides the possibility of stepwise startup)

seal, which is capable to provide non-exceeding of nominal leakage (50 L/h) during RCP set trip without cooling for 24 hours at nominal parameters of the primary circuit

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Main Reactor Plants Data Main Reactor Plants Data Comparison Comparison

Parameter

V-320 V-428 v-412

V-466B

Thermal power (nom.), МW Мощность тепловая (ном.), МВт

3000 3000 3000

Steam capacity under nominal conditions, Т/h Паропроизводительность в номинальном режиме, Т/ч

1470х4 1470х4 1470х4

Pressure of steam generated under nominal load at SG steam header outlet, МPа Давление генерируемого пара при номинальной нагрузке на выходе из коллектора пара ПГ, Мпа

6,27 6,27 6,27

Temperature of steam generated under nominal load, С Температура генерируемого пара при номинальной нагрузке, С

278,5 278,5 278,5

Design RP main equipment service life, year Срок службы основного оборудования РУ, лет

30 40 60

1919


Parameter Параметр

V-320 V-428 v-412

V-466B

Reactor / Реактор

Reactor pressure (nominal) at reactor core outlet, МPа Давление в реакторе (номинальное) на выходе из активной зоны, МПА

15,7 15,7 15,7

Coolant temperature at the core outlet, С Температура теплоносителя на выходе из активной зоны, С

320 321 321

Coolant temperature at the core inlet, С Температура теплоносителя на входе в активную зону, С

290 291 291

Coolant flow rate through reactor, m3/h Расход теплоносителя через реактор, м3/ч

84800 86000 86000

2020



V-320 V-428 v-412

V-466B

Reactor vessel/ Корпус реактора

Inner diameter (cylindrical part), mm Диаметр внутренний (цилинрическая часть), мм

4150 4150 4195

Wall thickness in the area of the core, mm Толщина стенки в районе активной зоны, мм

192,5 192,5 195

Length, mm Длина, мм

10885 11185 11185

Number of CPS control rods, pcs Количество ОР СУЗ, шт.

61 85-121* 85-121*

2121



V-320 V-428 V-412

V-466B

Steam generator Парогенератор

ПГВ-1000 ПГВ-

1000М ПГВ-

1000МK Inside diameter of steam generator vessel, m Внутренний диаметр корпуса парогенератора, м

4,0 4,0 4,2

Type of pump Тип насоса

ГЦН-195 ГЦНА-1391

ГЦНА-1391

Capacity, m3/h Подача, м3/ч

21200 21500 21500

Pressure head, МPа Напор, МПа

0,64+0,02 0,64+0,02 0,64+0,02

2222

Conclusion Conclusion

RP design meets the up-to-date requirements and can be licensed for construction

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BELENE NPP Reactor plant V-466B