資料2 - China Institute of Atomic Energy China National Nuclear Corporation 2017-9-14
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1. Overview about nuclear energy of China 2. SFR Development 3. Other Gen-IV Reactor Development 4. Conclusion 1
• 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
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 9
Phases 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 10
Engaged 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 14
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 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 15
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 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 16
Over 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 17
Overhaul 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 19
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
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 21
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 22
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 Reactor core thermal- Core seismic defamation System dynamic analysis code Inter subassembly nature hydraulic analysis analysis circulation flowrate 23
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
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 CFR1200 diagram based super-critical CO2 5. More advanced safety design will be considered 25
Generally Configuration of the Main Heat Transfer System of CFR1200 26
Suggested 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 27
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• R&D status of Gen-IV 29
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• 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). 31
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. 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. 34
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
• 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 36
CiADS 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 38
Parameters 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 39
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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. 41
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