China Institute of Atomic Energy China National … Institute of Atomic Energy China National...
Transcript of China Institute of Atomic Energy China National … Institute of Atomic Energy China National...
1. Overview about nuclear energy of China
2. SFR Development
3. Other Gen-IV Reactor Development
4. Conclusion
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• China primary energy consumption is about 4.18 billion tons of standard coal in 2016, decrease0.79%。
• Crude oil, natural gas, and non-coal electricity consumption amount is about 109.8 million tons ofstandard coal. Coal consumption fell by about 143.6 million tons of standard coal.
Energy type Electricity
generation (*1012kW.h)
Ratio Increase
(compare to 2015)
Coal 4.3958 74.4% 2.6%
Hydro 1.0518 17.8% 5.9%
Wind 0.2113 3.5% 19.0%
Solar 0.0394 0.7% 33.8%
Nuclear 0.2127 3.6% 24.1%
Total 5.9111 4.5%
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• The NPPs unites under operation is 35 (not include Taiwan region) till 31 December, 2016. And another 19 unites are under construction.
• The nuclear capacity is 33.6GW which is about 2.04% of total capacity.
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• In 2016, China's electricity industry generated a total of 5.91 trillion kilowatt-hours, including 212.7 billion kilowatt-hours of nuclear power. And the nuclear grows 24.1% from 2015.
• The average utilization of nuclear power plant in China has declined for three years. In 2014, the average utilization rate of 22 nuclear power plants in China was 86.32%. In 2015, the NPP units increased to 28, and the average utilization rate dropped to 83.3%. In 2016, the NPP units reached to 35, but the average utilization rate fell to 79.55%. The operation time is 6,987 hours a year, which was nearly 300 hours shorter than the previous year.
• The reason are mainly: the national economy is in a period of adjustment; balance of the energy resource adjustment.
Electricity generation in 2016
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• Energy policy – National Plan for Coping with Climate Change, to guarantee the
realization of the target of cutting the carbon emission intensity by 40 to 45 percent by 2020 from the 2005 level.
• Nuclear energy policy – The nuclear energy development should be sustainability, safe and with
high efficiency.
– Could provide a large scale nuclear power plant capacity in a limited time.
– The high level radioactive waste should be minimized.
– The roadmap of the nuclear development is tree steps: thermal reactor, fast reactor and fusion.
– The strategy of nuclear fuel cycle should be : the Closed fuel cycle based fast reactor.
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• The Electric Power Development “13th five years” plan (2016-2020) was issued in 2016. The plan indicate that nuclear power will be put into operation with the capacity about 30GW and another 30GW will be under construction. The total capacity will reach to 58GW till 2020.
• The studies of the Chinese Academy of Sciences (CAS) show that the nuclear power installation will reach to 200GW by 2030, and more than 400GW by 2050.
45%
10% 10%
15%
19%
Energy structure in 2050
Coal
Oil
Gas
Nuclear
Renewable
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Experimental Fast Reactor
CEFR Demonstration Fast Reactor
CFR600 Commercial Fast Reactor
CFR1200
2011 ~ 2023 ~2030
safety theory certification Scientific certification Fuel and material study Training and experience feed back
Industry scale to demonstration the closed fuel cycle
Safety Verification of large size SFR
Master of the large size SFR design and construction technology
Economic certification of large size SFR in China
Commercial operation Breeding nuclear fuel industrially Serially developing
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Phases CEFR CDFR CCFR
Power(MWe) 20 600 ≥1000
Coolant Sodium Sodium Sodium
Primary system Pool Pool Pool
Fuel (UO2)
MOX MOX Metal
Clad material Austenitic stainless
steels Austenitic stainless steels
CN-1515 Austenitic stainless steels
(ODS)
Core outlet temperature(C)
530 540 550
Liner power density(W/cm)
430 430 450
Maximum burn-up(MWd/kg)
60-100 80-120 120-150
Spent fuel storage Primary storage in
vessel and Water pool temporary storage
Primary storage in vessel and Water pool
temporary storage
Primary storage in vessel and Water pool temporary
storage
Safety system Active shutdown system
Passive DHRS
Active and passive shutdown system
Passive DHRS
Active and passive shutdown system
Passive DHRS
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Basic technical R&D
(1965—1987)
Applied technical
R&D(1987-
1992)
Engineering
technical R&D
(1992—2012)
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Engaged in the basic theory of SFR and the
principally experiments R&D
Engaged in the applied technical R&D oriented
to the engineering
Engaged in the design and the construction of
CEFR
• The SFR technical R&D started from the 1960’of the last century
• 14 facilities about neutron, thermal-hydraulic, sodium, fuel and material have been constructed.
• 1970.6.29,DF−VI, the first zero power experiment facility get the first criticality
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• The R&D of SFR supported by the national high technology program “863”
• 61 programs were carried out by the CIAE and other universities, institutes and factories
• More than 20 experiment facilities and loops were constructed
• Some computer code developed
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• Supported by the “863”program,focus on constructing an experimental sodium fast reactor with 65MW thermal power and 20MW electrical power, it is called CEFR
Site of CEFR:South
west of Beijing city
about 45km
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Parameter Unit Value Parameter Unit Value Thermal Power MW 65 Primary Circuit
Electric Power, net MW 20 Number of Loops 2
Reactor Core Quantity of Sodium t 260
Height cm 45.0 Flow Rate, total t/h 1328.4
Diameter Equivalent cm 60.0 Number of IHX per Loop
2
Fuel MOX (first loading is
UO2)
Secondary Circuit
Linear Power max. W/cm 430 Number of Loop 2
Neutron Flux n/cm2·s 3.7×1015 Quantity of Sodium t 48.2
Bum-up, first load max.
MWd/t 60000 Flow Rate t/h 986.4
Inlet/outlet Temp. of the Core
℃ 360/530 Tertiary Circuit
Diameter of Main Vessel(outside)
m 8.010 Steam Temperature ℃ 480
Design Life A 30 Steam Pressure MPa 14
Flow Rate t/h 96.2
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No Content date
1 Project approved 1995.12.29
2 Primary design approved 1997.11.4
3 FCD 2000.5.30
4 Closed of the nuclear island building 2002.8.15
5 Installation finished 2008.12.25
6 Satisfy all the requirement for the first loading 2009.9.27
7 Fist physics criticality 2010.7.21
8 The B stage commissioning work finished 2010.11.30
9 Fit the project target: Connect to the national grid firstly
and 40% rated power operation 24 hours 2011.7.22
10 Restart carry out the power operation experiment 2014.3.14
11 40% power planed experiment finished 2014.5.19
12 Achieve the 100% rated power firstly 2014.12.18
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2014.3 2014.12
restart,2 test in low power
Loss of vacuum test at 40% level
Load shedding test at 75% level
Over power protection test at
50% level
First time Operation 72h 100% power
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• CEFR operated 23days at 39MWt level in 2016.
• The main work to CEFR is overhaul include
– Primary and secondary sodium pump maintains
– Fuel handling machine maintains
– Thermal insulation system upgrade
– Conventional island maintains
– DCS upgrade
– Maintenance and repair of nuclear island auxiliary system
– Instrument and industrial television system repair and rectification
– Radiation monitoring system repair and rectification
– Electrical system repair and rectification
– Safety system and reactor protection system rectification
Water side of SG
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Parameters Value
Thermal Power, MW 1500
Electricity Power, MW 600
Efficiency 40%
Design load factor 80%
Fuel MOX
Burnup (max),MWd/kg 98
BR 1.15
Circuit Number per loop 2/2
IHX number per circuit 2
CDF <10-6
LERF <10-7
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1. Try to Fit the GIF Technical Requirement on The Safety and reliability
2. So the off-side emergency could be not necessary from the design
3. D-rap methodology is used in the design of CFR600
4. Ensures good inherent safety.
5. No large positive reactivity insertion at operating conditions or accident conditions.
6. Two independent shutdown system with one passive additional.
7. Decay heat removal system at operating conditions and accident conditions.
8. Primary and secondary Containment design
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1. “Suspend liquid” passive shutdown system
2. Passive Decay Heat Removal System connected with the hot pool
3. Passive Reactor vessel overpressure protection system
4. “Siphon” device to prevent large amount primary sodium leak after primary pipe break
5. Passive sodium leak stoppage system to mitigation the large water-sodium reactor accident
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1. System Transient Analysis Code
2. Core and Primary Circuit Thermal-Hydraulic Design code
3. Decay Heat Removal Capability Analysis Code
4. Severe Accident Analysis Code
5. Core Damage Evaluation code
6. Fuel subassembly characteristics evaluation code for the whole operation state
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hydraulic analysis Inter subassembly nature
circulation flowrate
Core seismic defamation analysis
System dynamic analysis code
Parameter Value
Thermal power,MW ~2900
Electric power,MW 1200
Thermal efficiency ~41%
Loading factor >85%
Design life,year 60
Fuel MOX ( (TRU,U)O2 )
Cladding ODS
Maximum burn-up,MWd/kg 150
Breading ratio 1.2
Loops per circuit 4/4
CDF <10-6
LERF <10-8
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Main Technical Features of CCFR
1. An innovative pool-type advanced SFR
2. Plant is designed to meet the requirements of the Generation IV nuclear energy systems.
3. More design solutions will be considered, including supercritical CO2 conversion.
4. The technical selection will be consider the continuity with the CDFR
5. More advanced safety design will be considered
CFR1200 diagram based super-critical CO2
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2015 2035 2020 2025 2030
Jan2015–Dec2020
Pre-concept Design Jan2021–Dec2024
Concept Design
Jan2025–Dec2028
Preliminary Design Jan2029–Dec2034
Detail Design
Construction
Dec2028
FCD
Dec2020
Decided to build
Dec2034
operation
Suggested Design Schedule for CCFR
• The Technology Roadmap (2002), defined and planned the necessary R&D and associated
timelines to achieve these goals and allow deployment of Generation IV energy systems after
2030. This roadmapping exercise was a two-year effort by more than 100 international experts
to select the most promising nuclear systems. In 2002, GIF selected the six systems listed below,
from nearly 100 concepts, as Generation IV systems:
• gas-cooled fast reactor (GFR);
• lead-cooled fast reactor (LFR);
• molten salt reactor (MSR);
• sodium-cooled fast reactor (SFR);
• supercritical-water-cooled reactor (SCWR);
• very-high-temperature reactor (VHTR).
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China SCWR design concept with pressure vessel---CSR1000
Parameters Value
Thermal power 2300MW
Electric power ~1000MWe
Efficiency ~43%
Operating pressure 25MPa
Design pressure 27.5MPa
Reactor inlet temperature 280℃
Reactor outlet temperature 500℃
Reactor flow rate 4284t/h(1190kg/s)
Loop number 2
Cycle direct once through
Coolant flow-path Two-pass
Design lifetime 60 years
SCWRs are high temperature, high-pressure, light water reactors that operate above the thermodynamic critical point of water (374°C, 22.1 MPa). The reactor core may have a thermal or a fast-neutron spectrum, depending on the core design. The concept may be based on current pressure-vessel or on pressure-tube reactors, and thus may
use light water or heavy water as a moderator.
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SCWR Main Features • High efficiency (up to 48%)
• Simplification of plant components and layout • Design flexibility
R&D and Chief Designer
• Nuclear Power Institute of China
Key Laboratory for nuclear fuel and materials
Key Laboratory for nuclear reactor thermal hydraulic technology
Key Laboratory for nuclear reactor system design
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• MSR Main Features • MSRs can be divided into two subclasses. In the first subclass, fissile material
is dissolved in the molten fluoride salt.
• In the second subclass, the molten fluoride salt serves as the coolant of a coated particle fuelled core similar to that employed in VHTRs.
• TMSR(Thorium Molten Salt Reactor) project
• Aims : Develop Th-Energy, Non-electric application of Nuclear Energy based on TMSR during coming 20-30 years.
• TMSR-SF(Solid-Fuel), a preliminary design.
• TMSR-LF(Liquid-Fuel), a conceptual design.
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Power 10 MWt
Lifetime 20 year
Operation time 100 EFPD for single batch of fuel
Average power density 4.0 MW/m3
Fuel element / abundant / 235U load 6cm ball / 17.0% /15.6 kg
Coolant( 1st loop, 2nd loop) FLiBe( 99.99%Li7), FLiNaK
Structure material N alloy, graphite
Reactor coolant inlet temperature 600 ℃
Reactor coolant outlet temperature 650 ℃
Vessel temperature / pressure designed 700C / 0.5MPa (abs.)
Vessel upper cover temperature designed <350℃
1st /2nd loop coolant flow rate 84 kg/s / 150kg/s
Cover gas / pressure Ar / 0.15MPa (abs.)
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• LFR Main Features • LFRs are Pb or Pb-Bi-alloy-cooled reactors operating at atmospheric pressure and at high
temperature because of the very high boiling point of the coolant (up to 1 743°C).
• The core is characterized by a fast-neutron spectrum due to the scattering properties of lead.
• In China, the Chinese Academy of Sciences (CAS) started in 2011 a new effort to develop an ADS. A new project CiADS(China initiative Accelerator Driven System) is suggested.
• CiADS Design parameters:Beam power250MeV@10mA; Reactor power10MW
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CiADS Project Owner Chinese Academy of Sciences Guangzhou Branch
Designer Institute of Modern Physics, CAS
partner Institute of High Energy Physics, CAS Hefei Institute of Physical Science, CAS CIAE CGN ……
325 MHz @IHEP Venus-II: Zero-power facility
• Milestones • 2014.06:site identified (Huizhou,
Guangdong Provence)
• 2015.12:Project proved by government
• 2017.04:Feasibility report review
• 2017.09:Preliminary design review
• 2017.10:Construction permission
• 2023.12:Operation
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• VHRT Main features • The VHTR is a next step in the evolutionary development of high-temperature gas-
cooled reactors.
• It is a graphite-moderated, helium-cooled reactor with thermal neutron spectrum.
• It can supply nuclear heat and electricity over a range of core outlet temperatures between 700 and 950°C, and potentially more than 1 000°C in the future.
• HTR-PM project • High Temperature Gas-cooled
Reactor-Pebble bed Modules
• Designer • Institute of Nuclear and New
Energy Technology(INET) of
Tsinghua University
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Parameters Design Value
Reactor power, MWt/MWe 250*2/212
Reactor pressure vessel inside diameter, mm 5700
Helium pressure of primary loop, MPa 7.0
Inlet/outlet helium temperature,℃ 250/750
Number of fuel elements in equilibrium core 420,000
Main feed-water temperature,℃ 205
Main steam temperature,℃ 571
Main steam pressure, MPa 13.9
Feed-water flow rate for one reactor steam generator, kg/s 98
Technical features:
‒ Inherent safety
‒ High thermal
efficiency
‒ Pebble-bed modular
‒ Short construction
period
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• China needs a significant nuclear energy capacity in future base on the forecast of the energy totally needed and the environment challenge.
• Nuclear fuel cycle is determined from the perspective of sustainable development of nuclear energy.
• China should develop the closed nuclear fuel cycle based on the fast reactor, and it is should be sustainable, safe, and economic.
• The stratagem of the nuclear energy development is thermal reactor, fast reactor and fusion reactor.
• The stratagem of the fast reactor development is CEFR, CDFR and CCFR. The main tasks of the FR in China are to Raising the utility ration of uranium resource and Transmutation of long life radioactive material. All these function will support a sustainability nuclear energy.
• Several other Gen-IV reactor type are under developing be different Chinese institute or universities.
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