RITM-200 Extended

r RITM Joint Stock Company “Afrikantov OKB Mechanical Engineering” eac t o plan t r r t plan o t eac RITM RITM r JSC “Afrikantov OKBM” RITM Reactor Plants for Nuclear-Powered Icebreakers and Optimized Floating Power Units

IN THE NUCLEAR ENGINEERING INDUSTRY SINCE 1945

JSC “Afrikantov OKBM” 15 Burnakovsky proyezd, Nizhny Novgorod, 603074, Russia Tel.: +7 (831) 275 26 40 Fax: +7 (831) 241 87 72 E-mail: [email protected] www.okbm.nnov.ru TABLE OF CONTENTS

From Past Experience to Future Prospects ��2 Nuclear-Powered Icebreakers of Russia ��4 NSSS for the Nuclear Icebreaker Fleet ��6 RITM-200 Reactor Plant for New-Generation Nuclear-Powered Icebreakers ��9 Design Concept ��10 Main Equipment ��12 Serial Production of Reactor Plants for the New-Generation Nuclear-Powered Icebreakers ��14 Reactor Plant Safety ��16 Competitive Advantages ��17 Perspectives on the Development of Reactor Plants for Nuclear‑Powered Icebreakers and OFPUs ��18 World’s First Multipurpose Nuclear-Powered Icebreaker ��20 In practice, the following tactics is adopted for operation of icebreakers — open-sea icebreakers, like Arktika, From Past Experience to provide escort for convoys in deep-water areas. Limited-draft icebreakers, like Taymyr, provide escort for convoys in shallow waters. In this case, the convoys have to be transferred from an open-sea icebreaker to a shallow-draft icebreaker and the other way around, which results in that the convoy and the icebreakers have to Future Prospects spend the time standing, and it has a negative effect upon the economic efficiency of cargo transportation. In addition to that, practically all the currently operating nuclear icebreakers powered by the OK-900A reactor plants are nearing the end of their service life. In order to ensure the timely and adequate replacement Russia is the only country in the world that has a civilian nuclear maritime fleet. Nuclear-powered icebreakers for the decommissioned icebreakers, construction of new ships is in progress, so that the national objectives ensure steady functioning of the Arctic transportation system for Russia to achieve its national objectives in the be achieved in terms of reinforcing and protecting the geopolitical interests of the Russian Federation in the Arctic region. Arctic region, and in terms of supporting the economic and business activities and living of population in the Far North regions of Russia. Diagram of cargo traffic on The Multipurpose Norther the Northern n Sea Rou Sea Route nuclear-powered te t ran sp icebreaker or t c or rid or

Диксон Хатанга Харасавэй Тикси

Дудинка Печенга Норильск Певек Яся Зеленый мыс Мурманск Индига Ямбург Игарка Ухта Якутск Архангельск Integrated layout The double draft makes the ice- of the SGU breaker multipurpose, i.e., capable Currently, Russian companies of operating both in deep waters are developing new-generation Лесосибирск and in shallow waters, while com- multipurpose nuclear icebreakers bining the features of an open-sea powered by the RITM-200 reactor and shallow-draft icebreakers. For plant, which has an integral layout such multipurpose icebreakers, of its steam-generating unit (SGU). The first Soviet nuclear-powered icebreaker Lenin was commissioned in 1959. It was the world’s first surface ship JSC “Afrikantov OKBM” has devel- with a nuclear propulsion plant unmatched in terms of its power among the nuclear-powered icebreakers world- oped the new-generation RITM wide. As the power source, the OK-150 nuclear steam supply system (NSSS) was adopted. It was a reactor plant with reactors. a distributed layout, i.e., the main equipment of the circuit was placed in individual pressure vessels connected via long pipelines. Starting from 1964, the development commenced of the OK-900 nuclear steam supply system (NSSS) with a modular layout, i.e., every reactor plant incorporated a pressurized water reactor, four circulation pumps, four steam generators, pressurizers and other equipment. The reactor, the pumps and the steam generators had individual pressure Open-sea Limited-draft vessels and were connected via short coaxial nozzles. The OK-900 NSSS was installed into the upgraded nuclear- nuclear-powered nuclear-powered powered icebreaker Lenin. In 1968, the USSR Council of Ministers made a decision to build the nuclear-powered ice- icebreaker Modular layout of the SGU icebreaker breaker Arktika. The OK-900 NSSS was re-designated as OK-900A because of individual differences in its interfaces with the nuclear-powered icebreaker Arktika. In the next phase, civilian marine nuclear steam supply systems with the KLT-40 and KLT-40M single-reactor plants were developed for a nuclear lighter-aboard ship and for two limited-draft icebreakers designed to ensure safe waterways for cargo ships in the mouths of Siberian rivers.

2 3 nuclear-powered lighter-aboard Nuclear-Powered icebreakers & ship 10 1 Ship’s specifications: Icebreakers of Russia length reactor plants displacement 22 draft ARKTIKA ROSSIYA SEVMORPUT

LENIN SIBIR

134 m 147.9 m 147.9 m 150 m 260.3 m 19,240 t 21,000 t 21,000 t 23,000 t 61,000 t 10.5 m 11 m 11 m 10–11 m 11.8 m SOVETSKIY SOYUZ VAYGACH YAMAL

TAYMYR 50 LET POBEDY

150 m 151.8 m 151.8 m 150 м 159.6 m 23,000 t 21,000 t 21,000 t 23,000 t 25,170 t 10–11 m 8.1 m 8.1 m 11 m 11 m

4 5 NSSS for the Nuclear JSC “Afrikantov OKBM” is a chief designer of reactor plants for the nuclear icebreaker fleet. Icebreaker Fleet

1959 1970 1975 1977 1985 1988 1989 1990 1992 2007 2020 2027 до 2030 NSSS type Rated reactor JSC “Afrikantov OKBM” has power been developing reactor plant designs for nuclear-powered Lider RITM-400 ships since 1954. 2×315 MW

1960 four serial multipurpose Order of Lenin for nuclear icebreakers RITM-200 the development 2×175 MW of the OK-150 Arktika reactor plant

Vaygach KLT-40М Taymyr 1×171 MW

Sevmorput KLT-40 1×135 MW

50 Let Pobedy

Yamal

Sovetskiy Soyuz 2010 ОК-900А Rossiya 2013 2×171 MW Twenty six nuclear reactors The designed by JSC “Afrikantov nuclear-powered Sibir 1992 icebreaker Lenin OKBM” for 13 ships were was the world’s rst 2008 manufactured totally surface ship with a Arktika (including 2 currently under nuclear propulsion construction). Moreover, plant. Lenin 1989 ОК-900 a part of the reactor plant 2×159 MW equipment was manufactured at the JSC “Afrikantov OKBM” ОК-150 production facilities. 3×90 MW

6 7 Generations of Marine Reactor Plants RITM-200 Reactor Plant for As of now, 3 generations of reactor plants have been developed for the civilian nuclear fleet. New-Generation Nuclear- Generation 1 Generation 2 Generation 3 Powered Icebreakers ОК-150 ОК-900 KLT-40 RITM-200 (ОК-900А) (KLT-40M) New-generation ARKTIKA multipurpose nuclear-powered icebreaker

173 m 24,800 t / 33,600 t 8.5 m / 10.5 m

Distributed layout of Reactor plant with the modular Reactor plant with the The lead nuclear-powered icebreaker Arktika with the reactor plant RITM-200 officially came into commission on the reactor plant layout of the steam-generating integrated layout of the steam unit (SGU) generating unit (SGU) October 21, 2020. The nuclear ship of the new project is the biggest and most powerful in the world. Due to the increased width, the multipurpose nuclear icebreaker alone is capable of escorting the tankers with a displacement of up to 70,000 tons in the Arctic region. The icebreaker can pave the way for ships through ice up to 3 meters thick. By 2021, the Russian fleet is to receive a series of new-generation multipurpose nuclear-powered icebreakers. They are designed to provide unassisted ice escort for ships, including large-capacity vessels, to lead convoys Main design characteristics in the Western Arctic region all year around; and in the Eastern Arctic region, during the summer and autumn months. The nuclear-powered ships will be suitable even for shallow waters of the Gulf of Ob and Yenisei in the Length at design waterline, m 160 Dudinka direction. ROSATOM is now constructing new multipurpose nuclear-powered icebreakers. Beam at design waterline, m 33 Molded depth, m 15.2 Icebreaking capability, m up to 3 Complement 75 Draft at design waterline (open-sea icebreaker mode), m 10.5 Minimum operating draft, m 8.5

8 9 Design Concept Rated Parameters

Primary circuit operating pressure, MPa 15.7

In the course of the design work on the reactor plant for the new nuclear-powered icebreaker, an integrated ap- Primary coolant temperature: proach was implemented to identify the basic parameters of the primary circuit, to select equipment and equip- – core inlet, °C 277 ment layout, and to adopt the optimum configuration and parameters for the safety systems. – core outlet, °C 313

Primary coolant flow rate through the 3,250 Fundamental Solutions reactor core, t/h

1. The nuclear propulsion plant incorporates two reac- 4. Passive and active safety systems are introduced. Steam output, t/h 248 tor plants based upon a 175 MWt integral pressurized 5. Safety of the RITM-200 reactor plant is based upon Steam parameters water reactors and placed into two individual contain- the following principles: – temperature, °C 295 ments. high heat-storage capacity, – pressure, MPa (abs.) 3.82 2. The steam is generated (248 ton/h in either reactor natural circulation of the primary coolant suf- Hydrostatic test temperature at the end of plant) through transferring the primary circuit heat to ficient for shut-down reactor cooling, 30 the secondary circuit feedwater and steam in a steam minimum length of the primary pipelines, service life, °C generator, i.e. by the traditional two-circuit schematic outflow restrictors used in small nozzles, Neutron fluence at the end of service life, well-proven in the nuclear power industry. compared to the modular schematic, the pri- 5.2×1019 n/cm2 3. The reduced neutron fluence to the pressure ves- mary coolant volume is large in the reactor sel makes it possible to extend the lifetime under ir- pressure vessel, which extends the time to radiation for the steam-generating unit (SGU) and to core dewatering in primary circuit LOCAs. Main design characteristics per 1 Steam reduce the hydraulic test temperature. Generating Unit (SGU)

Technical Features SGU type integrated Thermal power, MW 175 The integrated pressure vessel of the steam-gen- The lifetime and service life of the main equipment erating unit (SGU) allowed the reactor plant mass are extended. Capacity factor (as required in reactor plant 0.65 and overall dimensions to be reduced within the Compared to the marine reactor plants of previ- specifications) containment. ous generations, more extensive time margins are The low-enrichment reactor core comprised of an provided in emergencies for the personnel to take Continuous operation period, h 26,000 array of fuel assemblies ensures long-time opera- corrective actions. Initial core stored energy, TW-h 4.5 (7.0*) tion without recharging and satisfies the requirements of the nuclear weapon non-proliferation Fuel enrichment < 20% regime. Assigned service life: – permanent equipment, year 40 – replaceable equipment, year 20

Assigned lifetime: – permanent equipment, thousand hours 320 – replaceable equipment, thousand hours 160

*design prospects

10 11 Main Equipment Reactor Core

The design employs a reactor core comprised of an ar- Lifetime, h 75,000 ray of fuel assemblies incorporating cermet fuel with Service life, year 12 Steam Generating Unit (SGU) the uranium content increased vs. the intermetallic Dimensions: OD×H, mm ≈ 1,600×1,200 1 fuel. The reactor core satisfies the requirements of the Initial core stored energy, TW-h/m3 2.13 Underlying the RITM-200 reactor plant design is an nuclear weapon non-proliferation regime (the enrichment is below 20%). Number of fuel assemblies 199 2 integrated type steam generating unit (SGU) utilizing forced circulation. The SGU steam generator cassettes 235U load, kg 438 are placed inside the pressure vessel, and the primary Average fuel enrichment, % < 20 circuit circulation pumps (PCCP) are in individual ex- Average 235U consumption, g/MW-day 2.3 ternal hydrochambers. The SGU has scaled-up initial core stored energy. Compared to modular-type SGUs currently used in nuclear-powered ships with their Steam Generator steam generators placed in separate pressure vessels, the new SGU type features greater compactness. Ad- The reactor plant employs a high-efficiency straight-tube steam generator (SG). The specific steam output of the ditionally, in order to minimize the overall dimensions, steam generator is more than two times higher than that of the currently used coil-tube steam generators. The a more compact steam generator design has been configuration of the steam generator cassettes makes it possible to arrange the cassettes compactly within the used, a core comprised of an array of fuel assemblies steam generating unit pressure vessel. 4 3 has been introduced, which has a higher uranium content, and the equipment has been arranged more Number of SG cassettes 12 densely in the compartment. The compactness of the Heated length, mm 2,000 steam-generating unit makes it possible to reduce the SGU mass and overall dimensions, which cuts down Heat exchange surface area, m2 93.4 the scope and duration of installation activities done in the shipyard and enhances the manufacturing qual- ity of the SGU thanks to the fact that all activities are Pumps completed at a machine building plant. At the same The primary circuit circulation pump (PCCP) is of a traditional design, vaned, single-stage with a canned electric time, the disposal of the facility is simplified thanks motor. The motor is single-wound. The pump rotation speed is controlled by changing the power supply current to the possibility of unloading the entire SGU with a frequency. 5 minimum scope of dismantling activities to be done. Control and Protection System Drive Mechanisms

The group of safety control rod drive mechanisms is designed to scram the reactor and to keep it subcritical in an emergency. Quantity The group of compensating group drive mechanisms is designed to compensate for the excess reactivity in the 1 — Control rod drive mechanism (CRDM) startup mode, in the power operation mode and in the reactor shutdown mode. The control and protection sys- Reactor core 1 2 — Control group drive mechanism (CGDM) tem drive mechanisms in the RITM-200 reactor plant are developed based upon the drives used in the KLT-40S 3 — Primary Circuit Circulation Pump (PCCP) Steam generator 4 reactor plant. 4 — Steam generator PCCP 4 5 — Reactor core Drive mechanisms: The distinctive features of the drive mechanisms in the RITM-200 reactor plant are: – CGDM 12 extended lifetime and service life – CRDM 6 increased travel length of the reactivity control members General view of the SGU

12 13 1 — Assembly of reactor plant tube units and devices Serial Production of companies in 2 — Corrosion resistant surfacing by welding on the shell with nozzles > cooperation Regular manufacturing cycle 3 — Forging of a workpiece on the automatic forging machine Reactor Plants for 15 Repetition and periodicity 4 — Hardening process for the shell workpiece reactor plants for of manufacturing process 5 — Machining of slanted holes to install steam nozzles the New-Generation 6 — Pressure vessel ingot castin a series of icebreakers Stable cooperation between 7 — Corrosion resistant surfacing by welding on the shell with preheating 10 6RPs have been manufactured enterprises 8 — Upright positioning and installation of the reactor plant pressure vessel into Nuclear-Powered a special building berth and supplied to the object 9 — Moving the finished pressure vessel into the shipping package Icebreakers 10 — Transportation of the reactor plant SGU pressure vessel 11 — Installation of the RITM-200 reactor plant

1 5 7 8 9

2 6

11 3 4 10

14 15 Reactor Plant Safety Competitive Advantages

Compared to the previous generation, the technical and economic Radiation and Environmental Safety performance and safety have been substantially enhanced; the mass

and size characteristics have been considerably reduced, which made The exposure dose for the crew during normal operation and in design-basis accidents is less than 0.01% of the it possible to develop a double-draft icebreaker. natural radiation background. Multiple uses are possible in ships, floating structures and within pow- The exposure dose to the population in a design-basis accident with severe core damage is below the values that er sources for various applications. require any protective actions to be taken. There is a potential for the reactor plant upgrading and for creating a The outside seawater activity associated with reactor plant operation is around 0.1 Bq/L, which is 100 times lower power range family of this type of reactor plants with broadening the than the regulatory value for the potable water activity. spheres of reactor plant applications. The radwaste volume is reduced by:

the use of the core comprised of an array of fuel assemblies — the amount of solid radwaste reduces RITM-200 reactor plant because no replacement is required for the reactor core pull-out assembly throughout the entire ser- ОК-900А RITM-200 vice life of the reactor plant, Assigned lifetime of the main equipment, h 100,000 (177,000*) 320,000 increased refueling intervals — the frequency of radwaste supplies accompanying the refueling is reduced, Assigned service life of the main equipment, year 25 (33*) 40 the non-waste technology system — the amount of liquid radwaste reduces by the primary water Mass of 2 reactor plants within the containment, t 2,603 2,200 circulation arranged in closed paths during maintenance operations with the primary circuit system. Overall dimensions of the reactor plant containment L×W×H, m 7.6×13.3×20 6×13.2×15.5 Initial core stored energy, TW-h 1.8 4.5 (7**) Safety Barriers *maximum value reached during operation **maximum design value

Engineering Solutions Different from Those in Current Reactor Plants:

4 passive emergency pressure release systems and emergency shutdown reactor cooling system (the effectiveness of the systems has been verified by rig testing) 5 external systems connected to the top part of the SGU 3 the primary coolant circulation path in a single pressure vessel collector circuit used for the primary coolant circulation

1 It is highly significant for ensuring reactor plant safety that passive and self-actuated safety systems and devices 1 — fuel composition are used, which limits adverse effects of failures in external systems, power supply and of human errors. The 2 — fuel cladding 2 design employs the passive devices and systems that function using natural processes and do not require any 3 — primary circuit external power supply. They include: 4 — reactor plant containment emergency core cooling system with hydroaccumulators that injects water to the reactor by the pressure 5 — safety enclosure produced by the gas blanket; one of the pressurizer groups is used as a hydroaccumulator containment with an emergency pressure release system capable of functioning in a passive mode Defense-in-depth (5 barriers preventing radwaste propagation)

16 17 Based upon the RITM-200 reactor plant, the concept of RITM-200M reactor plant design has been developed for an optimized floating power unit (OFPU). The OFPU is an energy generating facility in the form of a non-self- Perspectives on the propelled ship that incorporates two RITM-200M power plants. Such mobile power unit can generate electricity or ensure cogeneration of electricity and heat for household and industrial consumers. Development of Reactor While ensuring independence from the limitations of traditional energy-carrier resources, these power units will be a powerful factor in sustainable development of any region that is not covered by the unified power system Plants for Nuclear‑Powered and that requires reliable and economically acceptable energy carriers. Icebreakers and OFPUs Basic design characteristics of the RITM-200M reactor plant Generator electric output, MW 2×50 Steam output, t/h 280 The promising areas for the development of the Northern Sea Route in Russia include providing year-round navi- 235U enrichment, % below 20 gation of ships from the Barents Sea to the Sea of Okhotsk and operating in shallow-water areas in the Arctic Ocean basin. Achieving the objective of upkeeping drilling rigs is entrusted to the advanced off-shore nuclear Period of operation to core refueling, year 10–12 icebreaker having the draft of 8.5 m and powered by the RITM-200B reactor plant. The objective of providing Containment overall dimensions for 2 reactor plants, 6.8×14.6×16.0 year-round navigation along the Northern Sea Route is entrusted to the nuclear-powered icebreaker Leader that L×W×H, m is capable of going through the ice up to 4 m thick and leading large-capacity ships. Mass of 2 reactor plants, t 2,600

JThe development of the RITM-200B reactor plant design for the off-shore nuclear-powered icebreaker and of RITM- Basic design characteristics of the OFPU 400 reactor plant design for the icebreaker Leader is underway in JSC “Afrikantov OKBM”. Underlying the reactor plant designs is a unified set of engineering solutions used in the reactor plant for the multipurpose nuclear-pow- Length, m 112 ered icebreaker, in particular: integral configuration of the primary circuit equipment; Beam, m 25 compact once-through steam generator; General view of the RITM-200M SGU Draft, m 4.5 core comprised of an array of fuel assemblies with extended lifetime and service life; Displacement, t 12,000 maximum unification with the RITM-200 reactor plant in terms of the refueling complex. Basic Design Characteristics of the RITM-200B The developed reactor plant designs and RITM-400 reactor plants have good prospects for being used Nuclear-powered both in nuclear-powered icebreakers icebreaker with the RITM-200B RITM-400 and in land-based/floating small-sized RITM-400 reactor plant Thermal power, MW 209 2×315 nuclear power plants. Number of reactor plants 1 2 Propeller power, MW 40 120 Nuclear-powered Overall dimensions of the reactor plant icebreaker with the 6×7×16 8.2×9×17 in the containment, m RITM-200B reactor plant Reactor plant mass in the containment, t 1,453 2×1,945 Multipurpose Overall service life, year 40 40 nuclear-powered Optimized oating icebreaker power unit with the The experience that JSC “Afrikantov OKBM” has accumulated in the devel- RITM-200M reactor plant opment of the marine reactor plants enables development of reactor plants General view of the RITM-400 SGU for floating power units (FPU).

18 19 World’s First Multipurpose Nuclear-Powered Icebreaker

2020 — the multipurpose nuclear icebreaker Arktika with the RITM-200 reactor plant commenced its operations. 2022 — the nuclear fleet will get two more serial multipurpose nuclear powered icebreakers Sibir and Ural. By 2027, it is scheduled to construct two more serial icebreakers of this project.

Nikita Greidin’s photos are used 20