SVBR 75/100 nuclear reactor
SVBR 75/100 nuclear reactor
SVBR 75/100 nuclear reactor
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CONTENTS<br />
CO-generating water-desalinating facility powered by <strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> NUCLEAR 1<br />
REACTOR<br />
Design organizations involved in the project 1<br />
Layout of co-generating <strong>nuclear</strong>-powered water desalinating facility 2<br />
Performance of co-generating <strong>nuclear</strong>-powered water desalinating facility 2<br />
Transportable <strong>reactor</strong> unit 3<br />
<strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> REACTOR 4<br />
<strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> REACTOR SAFETY CONCEPT 5-6<br />
Coastal power-generating facility 7<br />
Water-desalinating facility 7-8<br />
Economic indices of <strong>nuclear</strong>-powered water desalinating facility 8<br />
CO-GENERATING WATER-DESALINATING<br />
FACILITY POWERED BY<br />
<strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> NUCLEAR REACTOR<br />
PURPOSE – electric power generation and desalination of sea water<br />
FIELD OF APPLICATION – regions with low level of power-generation infrastructure<br />
DESIGN ORGANIZATIONS INVOLVED IN THE PROJECT<br />
FSUE OKB “GIDROPRESS” - General Designer of <strong>SVBR</strong> -<strong>75</strong>/<strong>100</strong> <strong>reactor</strong><br />
Russian Research Centre IPPE - Scientific Supervisor<br />
FSUE SPbAEP – Architect Designer of <strong>nuclear</strong>-powered water desalinating facility<br />
FSUE SPMBM «Malakhit» - General Designer of transportable <strong>reactor</strong> unit<br />
FSUE Central Research Institute named after A.N.Krylov – Designer of water desalinating<br />
facility comprising a distillation water desalinating plant (DDP) and reverse osmosis waterdesalinating<br />
plant (RODP)<br />
1
LAYOUT OF CO-GENERATING NUCLEAR-POWERED WA-<br />
TER DESALINATING FACILITY<br />
replaceable transportable <strong>reactor</strong> unit<br />
stationary coastal power-generating facility<br />
1 – transportable <strong>reactor</strong> unit<br />
2– protective dry dock<br />
3 – building for steam-turbine plant<br />
4 – building for desalinating plant pumps<br />
5 – water-desalinating plant modules<br />
6 – desalinated water storage tanks<br />
7 – platform for <strong>reactor</strong> coolant solidification prior to<br />
transportation<br />
8 – office building<br />
PERFORMANCE OF CO-GENERATING<br />
NUCLEAR-POWERED WATER DESALINATING FACILITY<br />
Thermal power of <strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> <strong>reactor</strong>, MW 280<br />
Service life of transportable <strong>reactor</strong> unit to elapse before replacing, years 8<br />
Maximum capacity of fresh water, m 3 /day 200 000<br />
Production cost of fresh water, $/m 3 0,74<br />
Electric power of <strong>nuclear</strong>-powered water desalinating facility with TG operating in the 80<br />
mode of condensing, MW<br />
Power output into grid at maximum capacity of fresh water production, MW 9,5<br />
Production cost of electric power, $/kW*h 0,035<br />
2
TRANSPORTABLE REACTOR UNIT<br />
TRANSPORTABLE REACTOR UNIT resembles a replaceable “<strong>nuclear</strong> storage battery”.<br />
The transportable <strong>reactor</strong> units (TRU) are replaced as soon as <strong>reactor</strong> fuel cycle terminates and<br />
they are supplied according to the principle: Construction – Ownership –Leasing for a period determined<br />
by <strong>reactor</strong> core cycle (at least 8 years). Supplier runs all the financial and radiation risks<br />
of TRU construction, transportation, operation and probable accidents.<br />
The transportable <strong>reactor</strong> unit:<br />
houses <strong>SVBR</strong> -<strong>75</strong>/<strong>100</strong> <strong>reactor</strong> and support systems<br />
can be shipped from the Supplier-country by sea to the coastal stationary facilities and<br />
back after <strong>reactor</strong> fuel cycle has terminated<br />
can be transported inside the water area of water-desalinating plant, to be installed in a<br />
permanent coastal protective structure<br />
can be operated as a part of co-generating <strong>nuclear</strong>-powered water desalinating facility till<br />
the end of fuel cycle<br />
Layout of TRU<br />
on board a carrier<br />
1 – transportable <strong>reactor</strong> unit<br />
2 – floating dock<br />
3
<strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> REACTOR<br />
The TRU contains a multi-purpose fast-neutron <strong>reactor</strong> of <strong>SVBR</strong>-<br />
<strong>75</strong>/<strong>100</strong> type with lead-bismuth coolant. <strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> <strong>reactor</strong> has<br />
been developed within the framework of conversion program for a<br />
unique Russian <strong>reactor</strong> technology applied in <strong>nuclear</strong> submarines.<br />
The well-proven engineering basis for <strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> <strong>reactor</strong> design<br />
is created by the 50-year experience in designing and operation of<br />
lead-bismuth <strong>reactor</strong>s for <strong>nuclear</strong> submarines and Russian experience<br />
in elaboration and operation of fast sodium <strong>reactor</strong>s.<br />
The design of multi-purpose <strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> <strong>reactor</strong> makes use of the<br />
following approaches and engineering solutions:<br />
fast <strong>reactor</strong> with chemically inert heavy liquid-metal coolant – eutectic lead-bismuth<br />
alloy – with a very high temperature of boiling and a low temperature of melting;<br />
integral layout of <strong>reactor</strong> primary equipment as a single unit (monoblock): no valves<br />
and pipelines for liquid-metal coolant, additional unit shielding is provided by placing the<br />
unit (monoblock) inside water tank of passive heat removal system;<br />
a possibility of applying different types of fuel (UO2, MOX-fuel with warhead or <strong>reactor</strong><br />
Pu, mixed oxide fuel with minor actinides - TRUOX-fuel, nitride fuel) without changes<br />
in <strong>reactor</strong> design and meeting safety requirements;<br />
side;<br />
two-circuit heat removal with natural circulation on the steam generator secondary<br />
normal operation and safety functions combined in <strong>reactor</strong> systems as much as<br />
possible;<br />
<strong>reactor</strong> main components are of modular design, a possibility is provided for their<br />
replacement and repair;<br />
small mass and overall dimensions of the <strong>reactor</strong> provide a possibility to fabricate it<br />
at the Manufacturer’s, supply to the NPP site and collect it by any kind of transport.<br />
4
<strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> RP SAFETY CONCEPT<br />
<strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> <strong>reactor</strong> meets the most stringent safety requirements<br />
(human error proof, fail-safe, proof against sabotage and other illintentioned<br />
human actions) due to <strong>reactor</strong> inherent safety resulting<br />
from <strong>reactor</strong> design and primary coolant properties:<br />
very high temperature of lead-bismuth coolant boiling (~1670 0 C) prevents accidents<br />
due to DNB in the core and provides for a possibility to maintain low primary<br />
pressure under normal operating conditions and in case of hypothetical accidents, if<br />
any;<br />
all primary equipment is housed inside a strong vessel with a protective housing<br />
to provide an integral (single-unit) layout. Small free space between the main vessel and<br />
protective housing prevents loss of coolant<br />
in case the integrity of <strong>reactor</strong> main<br />
vessel is lost (a postulated accident);<br />
the level of natural circulation of<br />
the primary and secondary coolant is<br />
sufficient for passive heat removal under<br />
cooldown conditions;<br />
<strong>reactor</strong> is located inside a tank<br />
filled with water. Passive heat transfer via<br />
vessel to the tank water provides passive<br />
<strong>reactor</strong> cooldown in case all active heat<br />
removal systems fail (a postulated combination<br />
of a series of initiating events)<br />
within at least 5 days of human non-intervention;<br />
negative reactivity feedbacks provide<br />
for power decrease in case of spurious<br />
CPS rod withdrawal in case of a<br />
postulated scram failure to a level that<br />
would not result in the core melt;<br />
<strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> <strong>reactor</strong><br />
5
a possibility of chemical explosions and fires due to internal causes is ruled out<br />
thanks to inherent safety as the lead-bismuth coolant keeps chemically inert in case of<br />
loss of circuit integrity and possible contact with water and air. The capability of leadbismuth<br />
coolant to retain fission products (iodine, caesium, actinides - except for inert<br />
gases) can considerably mitigate the radiological consequences of a postulated lossof-coolant<br />
accident;<br />
<strong>reactor</strong> coolant system design and a great difference in the density of steamwater<br />
mixture and lead-bismuth coolant prevent the former from getting into the core<br />
and provide effective steam separation in case of primary-to-secondary leaks in SG.<br />
Gas system condensers and pipelines with rupture disks connect the gas cavity above<br />
the level of lead-bismuth coolant and the water storage tank, limit pressure in <strong>reactor</strong><br />
vessel in case of SG leak and provide steam-water mixture condensation. The tank<br />
serves as a relief tank in this case;<br />
design of <strong>reactor</strong> in-vessel shielding, accepted values of boiler water quality<br />
parameters and assumed primary-to-secondary pressure ratio, its value being permanently<br />
higher in the secondary circuit, prevent the possibility of radioactive contamination<br />
of steam to be generated by the system not only under normal operating<br />
conditions but also in case of primary-to-secondary leaks. In case the tubes lose their<br />
tightness, leaks in SG are repaired by tube plugging with <strong>reactor</strong> taken out of service.<br />
Ingress of lead-bismuth coolant into tight tubes is prevented by SG design;<br />
low potential energy accumulated in the primary circuit (low primary pressure)<br />
only restricts the scale of possible <strong>reactor</strong> damage to external impacts. Protection<br />
against external impacts is ensured by placing <strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> <strong>reactor</strong> inside a tight and<br />
strong vessel in <strong>reactor</strong> hall, and the transportable <strong>reactor</strong> unit, in its turn, is located<br />
inside a shielding coastal structure (“dry” dock);<br />
no materials are applied that could evolve hydrogen either under normal operating<br />
conditions or in accidents;<br />
due to high safety inherent to <strong>SVBR</strong>-<strong>75</strong>/<strong>100</strong> <strong>reactor</strong>, even a postulated combination<br />
of such initiating events as <strong>reactor</strong> hall shielding destruction, damage of “dry” dock<br />
ceiling and a large break of primary gas system followed by a direct contact of leadbismuth<br />
coolant surface with atmospheric air, does not bring about <strong>reactor</strong> runaway,<br />
explosion and fire. Possible radioactive release is predicted to be below the level that<br />
might require evacuation of the local population;<br />
6
COASTAL POWER-GENERATING FACILITY<br />
receives the transportable <strong>reactor</strong> unit<br />
operates for as long as the <strong>nuclear</strong>-powered water desalinating facility does and is<br />
the property of the Customer Country<br />
employs local personnel, uses local resources and manufacturing facilities at construction,<br />
equipment installation and operation as much as possible<br />
The coastal structures of <strong>nuclear</strong>-powered water desalinating facility include: a protective “dry”<br />
dock with the system for transportable <strong>reactor</strong> unit on-site mounting, protective platform for <strong>reactor</strong><br />
cooling after the core life is over, turbine hall, control room, switchgears, water intake and spillway<br />
systems, water-desalinating plant, fresh water storage, startup-backup boiler room, infrastructure<br />
buildings, structures for physical protection of desalinating facility site.<br />
WATER-DESALINATING FACILITY<br />
The <strong>nuclear</strong>-powered water desalinating facility consists of two types of plants: distillation<br />
water-desalinating plant (DDP) of multi-stage evaporation and reverse osmosis water-desalinating<br />
plant (RODP). Installed capacity of water-desalinating plants of both types is<br />
the same and amounts to 50 % of the desalinating facility installed power, which is <strong>100</strong>000<br />
m 3 /day.<br />
Application of a combined scheme of water-desalinating plants (DDP+RODP) improves efficiency<br />
of desalinating facility with a simultaneous assurance of the required quality of produced water.<br />
Salt content in DDP desalinated water is 20 mg/l, salt content in RODP desalinated water is 200<br />
mg/l.<br />
The water intake and spillway structures are shared by DDP and RODP.<br />
Water, which cools the TG and DDP condensers, is used to dilute the discharged brine to ecologically<br />
acceptable parameters (< 50 g/l and 32 0 С).<br />
The DDP and RODP systems for preliminary cleaning of sea water are combined to a necessary<br />
extent.<br />
The warm brine, discharged from DDP, is used to heat up water supplied to RODP.<br />
Depending on the terms of the Contract, the water processed at the water-desalinating<br />
plants can:<br />
be subjected to additional treatment to be turned into potable water;<br />
additionally pass through the stages of purification to obtain distilled and twice distilled coolant<br />
for power plants;<br />
be used for irrigation with nitrogen, phosphorus, potassium added.<br />
7
As the quality of potable water shall correspond to the national standards or the standards of World<br />
Health Organization, the desalinated water to be turned into potable water, if necessary, shall be<br />
disinfected and saturated with compounds of calcium to meet the sanitary standards. It can also<br />
be saturated with carbon dioxide to meet the Customer’s requirements etc.<br />
Water is disinfected by chlorination (or by ozonization, which is more expensive), by ultra-violet<br />
radiation and treatment with argentum ions.<br />
The required backup for water-desalinating plant equipment will be defined as agreed with the<br />
Customer.<br />
ECONOMIC INDICES OF NUCLEAR-POWERED WATER DE-<br />
SALINATING FACILITY<br />
For the Customer the cost of construction and operation of <strong>nuclear</strong>-powered water desalinating<br />
facility amount to:<br />
capital costs ~ 260 M$, including:<br />
- coastal structures – $ 60 million;<br />
- DDP equipment – $ 120 million;<br />
- RODP equipment – $ 80 million;<br />
annual costs ~ 30 M$/year, including:<br />
- rent for the transportable <strong>reactor</strong> unit with account for shipment ~ 12 M$/year;<br />
- cost of NUCLEAR-POWERED water desalinating facility operation<br />
and maintenance ~ $18 million/year.<br />
Estimated cost of transportable <strong>reactor</strong> unit construction for the Supplier will be ~ $ 44 million<br />
including the cost of the first core loading.<br />
Pay-back period for the site-specific <strong>nuclear</strong>-powered water desalinating facility and crediting<br />
rate are determined by the Customer depending on the local tariffs for fresh water.<br />
For example, the price of fresh water being 1 $/m3, the project pay-back period being 12<br />
years, crediting rate to 10% a year can be acceptable<br />
The accepted rent for transportable <strong>reactor</strong> unit of 12 M$/year will<br />
make it possible:<br />
for the Supplier to attract investments for transportable <strong>reactor</strong> unit construction on the<br />
basis of commercial credit;<br />
for the Customer to provide competitive price of the products produced (for example, fresh<br />
water ~ 1 $/m3 and electric power ~ 0,035 $/kW*h) and commercial attractiveness of the project<br />
(for example, the pay-back period of the project is ~12 years at loan interest rate of ~ 10%)<br />
8