> Energetické bloky sovětské a ruské jaderné ponorkové flotily

valka.cz / 941[/url]
2
VVER / ВВЭР
OK-650VV / ОК-650ВВ
21-45
190
949 / 949
2
VVER / ВВЭР
OK-650B / ОК-650Б
21-45
190
945 / 945
1
VVER / ВВЭР
OK-650 / ОК-650
21-45
190
971 / 971
1
VVER / ВВЭР
OK-650B / ОК-650Б
21-45
190
955 / 955
1
VVER / ВВЭР
OK-650V / ОК-650В
21-45
190
685 / 685
1
VVER / ВВЭР
OK-650B3 / ОК-650Б3
21-45
190



Atomic submarines equipped with JR with the heat carrier from the liquid metal (TNTK) / АПЛ с жидкометаллическим теплоносителем (ЖМТ)




Surface ships / Надводные корабли



I know, that are the tables due to the number of types of soviet and Russian submarines nuclear-powered, incomplete.
I put it here but because I had the available materials that they can be relatively easily adjusted, and especially immediately use.
Preparation of a new table, in which all of the tips and its contents will still be extended (at this point at least power on the shaft), however, will take some time, but I am convinced that here in the historically short time of deliver.

Photos of the submarine K-3 Leniský komsomol" is taken from the Словари и энциклопедии на Академике

Photos of the submarine "Dmitry Donskoj" is taken from the photographic series and the short story "In Severodvinsk has started utilization of the atomic submarines of the project 941 ("В Северодвинске началась утилизация АПЛ проекта 941") with the subtitle "Akulu cut" ("АКУЛУ ПОРЕЖУТ")

I Have not the slightest idea in what section, subsection and I don't know where it actually should be. Because this theme refers to soviet and Russian submarines nuclear-powered, so I put it here. Well, and because it is not a submarine, I put on the beginning of the title většítko (>). It is on the moderátorech, as with this material disposed of..

the First generation of energy blocks of soviet submarines, nuclear powered

The works associated with the development of the first generation of nuclear parogenerátorů (АППУ - атомная паропроизводящая установка - atomic parogenerátor) accounted for many of the soviet enterprises and factories. Above all it entailed the creation of an energy block of the atomic ship, i.e. its own nuclear reactor, its systems and mechanisms, which secure his job. Scientific supervisor of the development work he was appointed an academician And.P.Aleksandrov, the chief designer of nuclear power equipment (JER) was appointed academician of H.And.Dolležal. For nuclear submarines has been selected reactor type VVER (water-water energetic reactor - ВВЭР - водо-водяной энергетический реактор, VVER is, according to the Russian terminology, such as PWR (Pressurized water reactor) is referred to in the U.S. and as the EPR in France and Germany). Work on this type of rector for a nuclear power plant started up in 1955. During the development of VVER created a number of questions concerning the thermal scheme of nuclear reactor (JR) and its parameters, a scheme of regulation of neutron processes in the JR, about the methods neutronovo-physical calculation of water-water JR, about the problems of deep burnup of nuclear fuel and the buildup of residues the fission of U236, about the creation of the thermal scheme of nuclear device, about the development of the scheme of automatic control of the nuclear device.

The result was malorozměrné nuclear energy device with high performance and capable of high mobility, which were the qualities needed for use on submarines. On the basis of this first atomic energy sources were gradually created four generation of nuclear energy facilities and a number of their modifications.

The creation of such a movement capable of a nuclear energy source was at that time a huge technical leap forward. But if we look at the JR for the submarine from the point of view of nuclear safety, should then device a number of shortcomings, which were the cause of a number of accidents and defects. For the period of use of the JR first generation there were four accidents with water-to-water JR (K-19 in 1961, K-11 in 1965, K-431 in 1985 and K-192 in 1989).

A fundamental shortcoming of the atomic energy facilities of the first generation from the point of view of their nuclear and radiation safety were:
- large spatial distribution and large volume elements of the first circuit;
- the use of large diameter pipes for interconnection of the individual components of the energy unit, i.e. JR, steam generators, pumps, heat exchangers, volume compensators, etc., which create serious problems in the organisation of protection in case of accidents the first circuit and also when the bursting of the numerous impulse tubes, which connect the first circuit with the check measuring apparatus;
- low reliability of the device due to its large external dimensions, on the one hand (in particular, electrical equipment which was permanently energized) and the high technology operating values on the other side (the temperature of the first circuit 3000 C, the pressure of the first circuit 200 atm, the temperature in the second circuit 2500 C, etc.);
- practically the absence of automation of processes of management of JR;
- low reliability and credibility check of the measuring apparatus;
- low reliability of the management system and protection of JR;
the lack of resistance of the third safety barrier (the part where are located the device, parogenerátor, pumps and control systems protection JR), lack of a reliable system of control of nuclear processes that take place in the reactor.

Any of the above listed shortcomings could cause a serious crash.

The boot apparatus, JR allowed to drive nuclear processes in the reactor after a period of time starting from the minimum value of the performance. To this point, i.e. from the value of the output "0" to the minimum, a nuclear reactor has been run "blind", i.e. the process execution was taking place according to a special program that calculated the operator, he ran alone and could be a human error the wrong. Low position trigger compensatory grids in connection with an imperfect handling equipment and the negligence of the operator JR later led to the accident on the submarine K-341 in the gulf of Čažma.

To date, all the submarines of the first generation decommissioned, are gradually odstrojovány and thus prepared for further utilization (utilization is such a special word, that most people much for the heart will not marry, for he too does not understand; translated into ordinary colloquial language are in fact scrapping or disposal).

Photos of the Russian submarine nuclear powered the first generation of project 627A "Kit" To-42 "Rostovský komsomolets"
it is taken from the website "Russkij podplav" . The author of the photo is unknown, on the above website she was placed In.Lipjanskij.

The scheme of the reactor is reproduced in the web pages Bellona 2.3 Ядерные энергетические установки.

The second generation of Soviet nuclear-powered submarine power units


The second-generation nuclear steam generator was built on the basis of experience from the operation of first-generation nuclear energy sources, with an effort to eliminate their defects and shortcomings. In the first stage, it was assumed that if the nuclear power plant (hereinafter only the NPP) is made of high quality pipelines, it will be possible to avoid serious accidents of the reactor itself and other components of the NPP.


Based on this opinion, the first and second generation NPPs paid special attention to the quality of the individual components, believing that this was sufficient to ensure sufficient safety of the entire facility. It was also believed that the projects were sufficiently dimensioned so that the possibility of supercritical pressures and temperatures was not considered, so no special attention was paid to the control and monitoring systems of the NPP or to the emergency protection systems.


The possibility of cooling the reactor by completely disconnecting it from the submarine itself was also not considered. Experience from the operation of the first generation NPP, where the problems of water flow between the first and second circuit (mainly through the steam generator) and also the water flow out (to the pump, instrument and secondary steam generator sections) brought problems, the scheme of the whole system was changed for the second generation NPP. Although the system remained loop-free, it was substantially modified with regard to the requirements of spatial design and reduction of the volume of the first circuit.


The most important changes made to the second generation nuclear power plant:


- a "piping in piping" scheme and a "connected pumps" scheme for the first circuit steam generator are applied;
- significantly reduced number of large diameter pipes that connect the basic components of the nuclear power plant (first circuit filter, volume compensators, etc.);
- virtually all piping (large and small diameter) moved to areas where there are no operators;
- substantial change of control-measuring devices and automation of nuclear power plants;
- a substantial increase in the number of remotely controlled devices and apparatus;
- switching to AC electric motors (these are much better efficient than DC electric motors);
- turbogenerators (as the basic energy source for electric generators) have become autonomous;


Despite all the measures and changes in the project, however, nuclear and radiation safety has still not been fully resolved. Since 1967, there have been three nuclear accidents on submarines equipped with second-generation nuclear power plants (on the submarine K-140 in 1968, K-320 in 1970 and K-314 in 1983).


The basic shortcoming of second-generation nuclear steam generators was the unreliability of basic equipment (active zones, steam generators, automation systems).


The nuclear power plant accidents that occurred were related to a breach of the hermeticity of the fuel cell shell, the flow of water from the first to the second circuit through steam generators and also due to a fault in the control automation or its inability to work reliably in extreme situations. These include situations that arose due to the failure of automation systems or the inability to work satisfactorily in such cases, when there was an unauthorized start-up of a nuclear reactor (this was the case of the K-140 submarine accident).


The problems associated with emergency cooling during complete disconnection from other submarine systems, ensuring the control of nuclear processes in the reactor when in a subcritical state (except when pulse starting equipment was used) and preventing complete drying of the core in the event of a severe breach of the tightness of the first circuit.


Photos of the Russian nuclear-powered submarine of the second generation of the project 671B "Pike-B" K-461 "Volk"
is taken from the website "Russkij podlav" and its author is I.Kurganov.

the Third generation of energy blocks of soviet submarines, nuclear powered

Designing the WEIR of the third generation was launched in the early seventies of the last century. This period was characteristic of the changed approach to nuclear facilities, which began to be understood as zaříření increased risk. Was developed the concept for the creation of a security system including a system of emergency cooling and localization of the accident. These systems have been calculated on the maximum possible accident that could arise immediate total destruction of the heat pipe in the area of its largest diameter.

EAT for submarines of the third generation were built according to the concept of a block diagram. From the point of view of safety has been using this concept solved a number of very important tasks.

EAT produced according to such a scheme works in a mode of natural circulation in the first circuit with a sufficiently high power levels of the reactor, which is important for the security of the heat system in the active zone in a partial or even complete interruption of the sampling of the energy sub. In this embodiment were compared with EAT the first and the second generation of confused pipes the pipes of the first circuit of the short pipes of large diameter (sleeves) that connect each of the basic parts of the device (reactor, parogenerátor, pumps). Nuclear facilities are equipped with a system bezbateriového cooling (система безбатарейного расхолаживания - ББР), which will automatically work in case of failure of the power supply.

Significantly has been changed the system of management and protection of the reactor. The impulse, the trigger apparatus of the reactor allows you to fully control the modes of the reactor at any power level, including podkritické area. For the compensation (emergency) elements in the reactor (which are the control rods - probably from the cadmium, as is usual in the "adult"reactors power plants, which absorb neutrons and thereby control or stop the fission reaction, is for the case of a crash used a system of spontaneous insertion, which is consistent with the above system bezbateriového cooling.Is here see the pursuit of a substantial increase in the safety of the reactor in critical situations, to avoid nuclear catastrophe in the cases where it fails and ceases to perform its function of the other device. Without the need for any further intervention from the outside i.e. in case of failure of electrical sources it comes to "spontaneous "' activities of a nuclear reactor regardless of its location, therefore, even when rolling over submarines (not here used earth's gravity).

Has been used a number of other technical innovations that have increased safety in the use of EAT.

The block arrangement of the WEIR has led to a reduction of the dimensions of the WEIR, increasing power and improving other utility parameters.

The main problems of the WEIR of the third generation from the point of view of security problems are the reliability of specific parts, especially those that are used in the active zone, blocks of cleaning and cooling. These elements are constantly stressed by cyclical processes occurring in a nuclear reactor when its running. It was established that when the block arrangement of the WEIR has to be sleeves, but also the other elements of the basic equipment of the reactor must have the same reliability and must be made in the same quality as your own vessel of the reactor.

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Finally, information about nuclear energy facilities for submarines of the third generation one more interesting fact.

On the website of the Czech nuclear society came out 28.may 2007 article, which documents I don't know and for now I wasn't looking for and therefore did not consider, I can imagine, however, that something like this might work. EAT from decommissioned submarines and especially fuel have in Russia. Interesting is also the conclusion of the article.

Reactors of submarines for peaceful energy

An unattended nuclear reactors will strengthen the Russian energy sector in this decade. The results of military research and development certified in a hunter-killer fleet and on the arctic ledoborcích is applied in the production of electricity for ordinary civil purposes ever since the year 2010. The ship for the first mobile maintenance-free nuclear source began to build in Severodvinsk on the shore of the White sea. Commercial operation will begin in 2010, said the head of the Russian agency for atomic energy (Rosatom) Sergei Kiriyenko.

"We want to take maximum advantage of the unique experience gained in the operation of nuclear icebreakers and submarines. Thanks to the compactness, mobility and modular assembly of their reactors will significantly reduce the terms of their production and supply, which represents an extraordinary competitive advantage,“ added Kiriyenko. "The existing 6000 reactor years of operation of naval reactors confirmed their absolute reliability," he recalled.

Reactors with an output of 200 to 800 megawatts will operate in automatic, unattended mode; are yet perfectly while protected from unauthorised access by third parties. Fuel after five to six years of traffic exchange in a specialized plant and on habitat will add a "fresh" source. New reactors can withstand an earthquake of magnitude eight on the Richter scale, the fall of the yak-40 and up to 160kilometrové gale. Use will be as common sources of electricity or energy for the desalination of sea water or oil platforms on the sea shelf.

Boss Kurčatovova research institute academician Yevgeny Velichov in Vienna this week pointed out that these experiences are applied in the civil sector only very slowly. The smaller reactors are the best and in addition fastest contribute to reducing the Russian dependence on natural gas, albeit the final solution to the energy problems of the planet can bring only the mastering of nuclear fusion, he added.

For more information:

The majority of Russian nuclear submarines, four of the six nuclear icebreakers and three cruisers each have two reactors. The fuel used in the Russian marine reactors the first two generations has been enriched to 21 percent, in part reactors of the third generation already at 45 percent and in atomic icebreakers even to 90 percent. In the active zone in the context of improving the performance of the amount of u235 amounts increased from the initial 50 first to 70 and now to 115 kilograms. Exchange of fuel is carried out every seven to ten years, informed the Russian Analytical center for non-proliferation of nuclear weapons. "The reactors on the submarines from the reactors on the ledoborcích in principle, no different, are only more compact," says Stanislav Golovinskij, technical director of the race Atomflot Murmansk maritime shipping, where these exchanges are carried out.

The Russian stocks of highly enriched uranium from the nuclear arsenals of roughly a thousand tons. Half in the framework of the Russian-american program "From megatons megawatts" (see press release-102) in the United states, revised to 2013, the fuel for current nuclear power plants. The remaining 500 tons is enough for the ship's reactors for many decades, said the Russian Analytical center for non-proliferation of nuclear weapons.

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Photo "the cut" submarine taken from article In.And.Lebedev published on the website PROAtom.ru - http://www.proatom.ru.

the Fourth generation of energy blocks of soviet submarines, nuclear powered

By this we get to the chapter, which is in the enumeration of the EAT shortest. I guess its scope to disappoint, this fact has but a few reasons. First of all, that EAT the fourth generation are currently in development. Moreover, definitely not the last reason of such absence almost any information about this device is also strict confidentiality of these technologies, and regardless of if they are developed in Russia, USA or anywhere else in the world.

Today they are essentially known only to the general requirements and the possible way of solution, how would such EAT might look and what it should be.

It is assumed that the WEIR of the fourth generation should be a monoblock (or integral scheme of arrangement). The whole EAT should be very compact, which brings considerable advantages in the fact that the localization of the heat system of the first circuit in a single space with other necessary basic elements to EAT allows you to make this device without the use of nozzles and large diameter pipes.

This WEIR are developed in accordance with regard to all the current safety requirements at nuclear facilities. Because it should be a really compact unit, which will be very difficult to repair (very poor access, cramped space), must be individual components made in the highest quality and at the same time, it must be designed and manufactured to work with extremely high reliability.

It is, unfortunately, everything, what I about had generation EAT for submarines (but not only for them) have so far managed to find out. So it is rather a look into the future..

Energy blocks of soviet submarines nuclear-powered with a heat carrier from the liquid metal

Specific categories of EAT are a EAT that for heat transfer using liquid metal in the first circuit (the thermal system of liquid metal - жидкометаллический теплоносител - ЖМТ). The difference from the reactor of type VVER is so essential, that these EAT yes not included in any of the above generations. Are a separate chapter.

Relocation of heavy reactors towards the front of the submarine allowed it to improve the inclination of the vessel with the use of such a placement of the individual elements of the submarine so that the central part of the submarine was possible to move into a space with reduced radiation hazards and at the same time to transfer the radar and the radio cabin on the lower deck.

EAT with the heat carrier from the liquid metal has the following advantages:
- many times lower the pressure in the primary circuit (only around 20 atm) compared with rekatory type VVER, which allowed to substantially reduce the mechanical tension in the design of the first circuit;
- use a higher pressure in the second circuit than in the circuit first, which ensures greater safety, because the transmission medium can, in the case of violation of the hermetičnosti from the first and circuit to the other;
- the possibility of to a greater extent the use of less alloy steel.

the Shortcomings of the EAT with the heat carrier from the liquid metal:
- the high price of the heat carrier and also its high weight;
- the need for periodic regeneration of the heat carrier to comply with the high purity;
- the need to continuously maintain a heat carrier in liquid form (i.e. molten), and even at the time when the submarine at the base, which makes routine maintenance much more complex.

The first submarine equipped with this EAT, too, occurred the nuclear accident. Its cause was contamination of heating media, more precisely the clogging of the ducts of the residues after the oxidation of the melt, giving rise to the průpalu the active zone.

First factory test a submarine at the time of factory test short test the use of reported as a low reliability because of the number of gross defects, that it was canceled and cut up. Her reactor, from whose active zone was not exempt nuclear fuel, was suffused furfuralem (5-hydroxymethyl - C6H6O3) and bitumenen (bitumen) is placed in the race "Zvězdočka" in Severodvinsk. EAT other submarines, which use the heat carrier from the liquid metal, naběhaly during 10 years of use of approximately 70 "reaktoro-years".

Nuclear reactor on the secondary neutrons with the heat carrier from an alloy of lead - bismuth was developed in the OKB (ОКБ - Особое конструкторское бюро - special design bureau) "Gidroprogress" ("Гидропресс") in Podolsku and in OKB mechanical Engineering in Nizhny Novgorod. The main advantage of this WEIR was his dynamics. The basic electric power grid was designed at a frequency of 400 Hz, which allowed to use the components of half the size and weight, at the same time but it turns out that their use is more complicated.

Learn to use the subs with the WEIR with the liquid metal was quite difficult. The peculiarity consisted in the fact that there was a danger of solidification of the melt, which would lead to damage to the nuclear reactor. In Zapadnoj Lice, where there was a naval base for submarines of this series, was to built a special coastal complex. It was built a boiler room to produce steam for the submarine, the moths were attached to a floating barracks, and a destroyer, which is intended to supply the steam from their boilers. In connection with the low reliability of offshore funds listed above, which should ensure the heating, was this EAT heated virtually all the time even from its nuclear reactor, who worked at minimum power.

The additional complexity in using've been polluting also the high automation of these submarines. All sections with the exception of two were without access operators. Control of all equipment and devices housed was implemented remotely from the control desk located at central station.

If we do not take into account the fact that the WEIR with the liquid metal had two nuclear accidents, these reactors are much safer than the VVER reactors using high pressure water.

Significantly higher security was the result of these facts:
- the high temperature of the boiling point of the heat carrier ( 1679°C) at low pressure in the first circuit, which excludes its pressurisation and explosion with the extrusion of the active fuel to the space outside the reactor;
- rapid zatuhnutím of the heat carrier in the dehermetizaci (solidifies at a temperature of about 125 C), which is excluded severe accident with loss of heat carrier;
- a relatively short time, emitting alpha particles of the heat carrier;
- the absence of leakage of aerosols with Polonium 210 (half life 138 days);
- the ability of liquid metal to keep it in a large amount of radioactive iodine in the event of damage to the packaging of the first circuit, whose dispersal in space is the biggest danger for the operator of the submarine;
- a small reactive margin reactor, which excludes the power mode of the uncontrolled launch of nuclear reactions by the action of instantaneous neutrons (neutrons that are emitted directly at the time of the reaction of fission of heavy nuclei) and also his ability to spontaneously reduce the performance in case of accident;
- pressure gradient (the course) between the various energy circuits is toward the first heading downward, which prevents blowout of the heat carrier from the first radius to the second.

These and many other arguments talk about the perspective of the types of EAT. Currently, designers solve problems associated with the "freezing" and "melt" the metal alloy in the device, however at present no ships or submarines with this type of WEIR are not produced.


Submarine project 705 Lira (the photo is from the electronic encyclopedia "Военная Россия").

Power blocks of Soviet surface-powered nuclear ships


JEZ "KN-3" ("& # 1050; & # 1053; -3") for surface ships (active zone type "VM-16" - "& # 1042; & # 1052; -16" was developed based on the use of JEZ for atomic icebreakers Their design is practically identical to the nuclear reactor OK-900 for nuclear icebreakers of the "Rossija" class.
The design shortcomings in terms of safety are practically the same as for the third generation nuclear power plant for submarines.


At present, nuclear-powered ships have the same problems as submarines. This is mainly due to the fact that during the development of nuclear-powered ships, the issues of building special bases for their maintenance were not addressed. Therefore, JEZ ships of the project 1144 (heavy missile cruiser powered by nuclear) "Admiral Ushakov" and "Admiral Lazarev" were used for a very long time without the necessary overhauls and upgrades, so they gradually lost the ability to supply the necessary amount of electricity, steam, etc.


Note: the other two ships of project 1144 are "Admiral Nachimov" and "Petr the Great"


The service life of the equipment has been exhausted too quickly, no funds have been set aside for its repair and renewal, so these ships have been decommissioned, preserved and are now "stored" in a port in the North Sea.


The need to transport minerals and hydrocarbons from hard-to-reach areas of the North and other parts of the world's oceans to secure energy and raw materials for Russia and other countries raises further questions about the development of new surface-powered nuclear power plants, especially in cargo ships.
These needs dictate the need to continue developing new JEZs, which must be more reliable, cost-effective and, most importantly, safer than those hitherto used.


Photo sources:
Heavy nuclear-powered missile cruiser project 1144 "Peter the Great" - photo is from http://u-96.livejournal.com/1093089.html
Ship connection and command of the project 1941 "Ural" - photo is from the site "Morskaja Kollekcija" www.warships.ru

Table for the first generation of energy blocks of soviet submarines, nuclear powered




Notes:
*01) reshaped submarine project 658M K-145 for the test missile complex D-9 with 6 missiles R-29
*02) after removal of the missile complex was the submarine K-19 "rearmed" for the testing of new development and basic fasteners for submarines
*02) after removal of the missile complex was the submarine K-55 and K-178 reworked on the coupling of a submarine
*04) 1 submarine based,but it wasn't completed
*05) all the submarines that were made as the Project 659" have been upgraded to the submarine "Project 659T"
*06) all the submarines that have been produced as a Project 675" have been upgraded to the submarine "Project 675M"
*07) submarine "Project 675M" upgraded to "Project 675MK"
*08) submarine "Project 675M" upgraded to "Project 675MU"
*09) submarine "Project 675MK" upgraded to "Project 675MKV".

Tabulka pro druhou generaci energetických bloků sovětských ponorek na jaderný pohon






*10) zabudován zdokonalený raketový komplex D-5U
*11) na 667AM modernizována ponorka K-140 pro zkoušky rakety TPH typu R-31
*12) na 667M modernizována ponorka K-420 pro zkoušky nadzvukových KR "Meteorit-M (2,5 - 3 M, 5000 km)
*13) na 667AT modernizovány ponorky K-253, K-395 a K-423 pro zkoušky podzvukových strategických KR "RK-55 Granat" vypouštěných z torpédometů
*14) na 667AN, také označovanou jako "Projekt 09774", přebudována K-411 na nosič miniponorek a "přezbrojena" vědeckou a výzkumnou apareaturou
*14) na 667AK přebudována K-403 na plovouvoucí laboratoř pro výzkum a vývoj perspektivních hydroakustických komplexů Akson-1
*16) na 667AK přebudována K-415 na plovouvoucí laboratoř pro výzkum a vývoj perspektivních hydroakustických komplexů Akson-2, nebyla ale dokončena
*17) Prozatím neumím rozlišit kolik které třídy bylo vyrobeno ponorek, pro třídy 671, 671A a 671K je udáván souhrn

Table for the third generation of energy blocks of soviet submarines, nuclear powered




*18) In some sources is reactor OK-650 referred to as OK-650A with a given power of 180 MW
*19) a work in progress, cut up before running on the water
*20) Based 20, completed 14
*21) Based 2, completed 1
*22) Based 14, complete 12
*23) the Two so far based submarine is produced, according to the treasury should be by the year 2014, the total number of 8 submarines of the
*24) Submarine TK-210 neměani not based keel, they were only part of the trunk
*25) TK-208 Dmitry Donskoj reworked from the project 941 for the exams SRK Bulava
*26) TK-208 Dmitry Donskoj again reworked from the project 941U for exams SRK Bulava.

Table for energy blocks with the heat carrier from the liquid metal soviet submarines, nuclear powered



*27) the reactor MB-40A and OK-550 is equivalent to
*28) 3 submarines of the Project 705 upgraded to Project 705K


This is the eleventh part, the follow will be:
- a more detailed table for the WEIR surface ships
- crash JR on submarines

It's all only about soviet and Russian submarines.

a little (or rather big) request: if anyone has any additional or clarifying information, so it is me, please tell.

Thank you

F..