資料２ - China Institute of Atomic Energy China National Nuclear Corporation 2017-9-14
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資料２
China Institute of Atomic Energy
China National Nuclear Corporation
2017-9-14
1. Overview about nuclear energy of China
2. SFR Development
3. Other Gen-IV Reactor Development
4. Conclusion
1
2
• China primary energy consumption is about 4.18 billion tons of standard coal in 2016, decrease
0.79%。
• Crude oil, natural gas, and non-coal electricity consumption amount is about 109.8 million tons of
standard coal. Coal consumption fell by about 143.6 million tons of standard coal.
Electricity Increase
Energy type generation Ratio (compare to
(*1012kW.h) 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%
3
• 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.
4
• In 2016, China's electricity industry generated a
total of 5.91 trillion kilowatt-hours, including Electricity generation in 2016
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.
5
• 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.
6
• The Electric Power Development “13th
five years” plan (2016-2020) was
Energy structure in 2050
issued in 2016. The plan indicate that
nuclear power will be put into
operation with the capacity about
30GW and another 30GW will be 19% Coal
under construction. The total capacity Oil
45%
will reach to 58GW till 2020. Gas
15%
• The studies of the Chinese Academy Nuclear
of Sciences (CAS) show that the Renewable
10%
nuclear power installation will reach 10%
to 200GW by 2030, and more than
400GW by 2050.
7
8
Experimental Fast Reactor Demonstration Fast Reactor Commercial Fast Reactor
CEFR CFR600 CFR1200
2011 ~ 2023 ~2030
Industry scale to demonstration
safety theory the closed fuel cycle
certification Safety Verification of large size Commercial
Scientific certification SFR operation
Fuel and material study
Master of the large size SFR Breeding nuclear
design and construction
Training and experience technology
fuel industrially
feed back Economic certification of large Serially developing
size SFR in China
9Phases CEFR CDFR CCFR
Power（MWe） 20 600 ≥1000
Coolant Sodium Sodium Sodium
Primary system Pool Pool Pool
（UO2）
Fuel MOX Metal
MOX
Austenitic stainless Austenitic stainless steels Austenitic stainless steels
Clad material
steels CN-1515 （ODS）
Core outlet
530 540 550
temperature(C)
Liner power
430 430 450
density(W/cm)
Maximum burn-
60-100 80-120 120-150
up(MWd/kg)
Primary storage in Primary storage in vessel Primary storage in vessel
Spent fuel storage vessel and Water pool and Water pool and Water pool temporary
temporary storage temporary storage storage
Active and passive Active and passive
Active shutdown system
Safety system shutdown system shutdown system
Passive DHRS
Passive DHRS Passive DHRS
10Engaged in the basic
Engaged in the applied Engaged in the design
theory of SFR and the
technical R&D oriented and the construction of
principally experiments to the engineering CEFR
R&D
Basic technical R&D Applied technical Engineering
R&D（1987- technical R&D
（1965—1987） 1992） （1992—2012）
11• 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
12• 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
13• 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
14Parameter 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
2
Loop
Fuel MOX (first Secondary Circuit
loading is
UO2)
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 MWd/t 60000 Flow Rate
t/h 986.4
max.
Inlet/outlet Temp. of ℃ 360/530 Tertiary Circuit
the Core
Diameter of Main m 8.010 Steam Temperature
Vessel(outside) ℃ 480
Design Life A 30 Steam Pressure MPa 14
Flow Rate t/h 96.2
15No 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
Fit the project target: Connect to the national grid firstly
9 2011.7.22
and 40% rated power operation 24 hours
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
16Over power Load
restart，2 test Loss of vacuum First time Operation
protection test at shedding test
in low power test at 40% level 72h 100% power
50% level at 75% level
2014.3 2014.12
17Overhaul 2016
Totally operation 3600hr, produce electricity 16.33 million kwh
18• 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 Water side of SG
– 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
19Parameters 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
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
211. “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
221. 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
Reactor core thermal- Core seismic defamation System dynamic analysis code
Inter subassembly nature
hydraulic analysis analysis
circulation flowrate 23Parameter 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
CDFMain 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
CFR1200 diagram based super-critical CO2
5. More advanced safety design will be
considered
25Generally Configuration of the Main Heat Transfer System of
CFR1200
26Suggested Design Schedule for CCFR
Dec2020 Dec2028 Dec2034
Decided to build FCD operation
2015 2020 2025 2030 2035
Jan2025–Dec2028
Jan2015–Dec2020
Preliminary Design Jan2029–Dec2034
Pre-concept Design Jan2021–Dec2024
Detail Design
Concept Design
Construction
2728
• R&D status of Gen-IV
2930
• 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).
31SCWRs 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.
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 China SCWR design concept with
Design lifetime 60 years pressure vessel---CSR1000
32 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 reactor Key Laboratory for nuclear fuel Key Laboratory for nuclear
thermal hydraulic technology and materials reactor system design
33• 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.
34Power 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
• 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
36CiADS Project
• Milestones Owner Chinese Academy of Sciences Guangzhou Branch
• 2014.06：site identified (Huizhou,
Guangdong Provence) Designer Institute of Modern Physics, CAS
• 2015.12：Project proved by government
partner Institute of High Energy Physics, CAS
• 2017.04：Feasibility report review
Hefei Institute of Physical Science, CAS
• 2017.09：Preliminary design review
CIAE
• 2017.10：Construction permission CGN
• 2023.12：Operation ……
325 MHz @IHEP Venus-II: Zero-power facility
37• 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
38Parameters Design Value
Technical features:
Reactor power, MWt/MWe 250*2/212
‒ Inherent safety
Reactor pressure vessel inside diameter, mm 5700
‒ High thermal
Helium pressure of primary loop, MPa 7.0
efficiency
Inlet/outlet helium temperature,℃ 250/750
‒ Pebble-bed modular
Number of fuel elements in equilibrium core 420,000
Main feed-water temperature,℃ 205 ‒ Short construction
Main steam temperature,℃ 571 period
Main steam pressure, MPa 13.9
Feed-water flow rate for one reactor steam generator, kg/s 98
3940
• 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.
4142
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