So, it turned out that the channel uranium-graphite reactor is not
suitable for use on submarines and surface ships. And with
pressurized water reactor, the situation is exactly the opposite: being
originally created for ships, it is still active
It is also actively operated on land.
In accordance with the new goals, the reactor has become larger and more powerful,
but the principle of operation remained unchanged. He was assigned the name
VVER is a pressurized water-cooled power reactor. Developer
VVER – Experimental Design Bureau “Gidropress”. First ground
ny installation with a VVER-210 reactor was launched in 1964 at the New
Vovoronezh NPP. The number “210”, as well as for RBMK-1000, reflects its
electrical power in megawatts. Installations with VVER were recognized
are promising, therefore, soon at the same Novovoronezh NPP
the VVER-365 reactor was launched, and then the VVER-440. But 440 megawatts
also did not become the power limit. On May 30, 1980, the reactor was launched
torus VVER-1000.
VVER-1000 became, along with RBMK-1000, one of the flagships of the
sky, and then Russian nuclear power, this project determined
VVER reactors generate about 50% of all “nuclear” electricity
Troenergy price Russia. Let’s consider in more detail how the energy
block with VVER. The main part of the VVER reactor – the core –
on, by analogy with ship reactors, into thick-walled steel
case. Fuel cassettes with nuclear fuel are not inserted here.
they are located in separate channels, as in the RBMK reactor, but stand close to
to each other, like a hexagonal honeycomb in a bee hive (see fig.
4.17, 4.18).
Figure 4.17 – Fuel assembly (FA) of a type reactor
VVER-1000
Figure 4.18 – Layout of fuel assemblies in the core of a type reactor
VVER
Water enters the reactor vessel, passes through the core,
heats up, but does not boil, as in RBMK. Heated water from the reactor
falls into the steam generator. Passing through pipes, this water ( water of the first con-
round) through a metal wall gives off heat to the water of the second circuit,
after which it is again pumped into the reactor. The water of the second circuit is converted
is fed into steam, which is fed to a steam turbine. How is the further
the process is described above: steam rotates the turbine shaft, the turbine shaft
rotates the rotor of the generator, and the generation of electricity occurs ck current. The steam leaving the turbine is cooled, as a result it
turns into water again. This water passes through the auxiliary
equipment and fed to the steam generator to turn back into
steam, – this is how the second circuit closes. Diagram of a power unit with a reactor
type VVER is shown in Fig. 4.19.
Figure 4.19 – Diagram of a power unit with a VVER reactor
Unlike RBMK, water does not boil in the primary circuit of a VVER. This is done
lano for reasons of radiation safety, since water
the first circuit is radioactive. And in the second circuit circulates non-
radioactive water (with chemical additives), from which it forms
Xia non-radioactive steam. This is the idea – a double-circuit
the scheme allows you to start up the turbine with ordinary, non-radioactive steam.
In order to prevent the primary circuit water from boiling, it supports
live a pressure of about 160 atmospheres (similar pressure exerts
a column of water 1600 meters high). Development plans for domestic
nuclear power engineering for the next period is based precisely on
VVER reactors. New VVER-1200 units (AES-2006 design) will
they can have an even higher electrical power (1170 MW), since
it is planned to increase the temperature of the primary circuit water, which will lead
to an increase in temperature and pressure of steam going to the turbine.
The AES-2006 project combines the results of dozens of scientific
research and development work. New installation
has safety systems that allow dose limitationexposure of personnel and release of radioactive substances into the environment
environment in conditions of abnormal operation, as well as
accidents. The installation is resistant to external sources of danger, including
including plane crashes and earthquakes.
Figure 4.20 – The first circuit of a nuclear power plant with
reactor VVER-1200
Figure 4.21 – Containment (containment) of nuclear power
installation with a VVER-1200 reactor
The fuel in the new reactor will be UO 2 , possibly
uranium-gadolinium fuel UO 2 -Gd 2 O 3 (gadolinium Gd is a a neutron absorber). By improving the design of fuel rods
managed to increase the amount of fuel loaded into the reactor.
Figure 4.22 – VVER-1200 Reactor Pressure Vessel and Fuel Assembly
(TVS)
AES-2006 design meets a high level of safety
required worldwide for future stations. Thanks to the efforts
national engineers, in the new NPP-2006 project they managed
achieve an unprecedented level of safety: for example, the likelihood of
the desired core damage is about 10 -6 per reactor
per year – this means that a severe accident can occur once in
a million years. For comparison, in the UK, the probability of getting into
RTA with traumatic or fatal outcome is 6 · 10 -3 per
car per year (it should be taken into account that nuclear reactors
there are much (!) less cars in the world).
Figure 4.23 – General view of two power units with VVER-1200 reactors