JAEA latest reactor design (GTHTR300) and its economic analysis
Aug. 25-28, 2015
Shoji TAKADADepartment of HTTR, JAEA
Economy of GTHTR300
Economic competitiveness
High temperature, High efficiency
Simplification (based on the safety feature)
Direct cycle gas turbine
Safety• Severe accident free
(Double confinement)
Power conversion• Horizontal
• No inter-cooling
• Adoption of existing technology
• Enhancement of reliability
Layout• Separation of power
conversion vessel and
heat exchanger vessel
• Enhancement of
maintainability
GTHTR300Electricity; 275MW (46%)
Outlet temperature; 850C
Core Design•New refueling method
(Sandwich shuffling)
•High burn-up
(120GWd/t)
•Refueling Interval of 2 years
(Periodic inspection
interval of 2 years)
Coolant flow path• Cooling the reactor vessel using outlet
coolant of the compressor
• Available to use low-alloy for LWR
reactor vessel
Turbine Generator
Core
Recuperator
Precooler
Reactor
Heat Exchanger
vessel Power conversion vesselControl valves
CompressorTurbine Generator
Core
Recuperator
Precooler
Reactor
Heat Exchanger
vessel Power conversion vesselControl valves
Compressor
2K. Kunitomi, et al., Design study on Gas Turbine High Temperature Reactor (GTHTR300), Trans. Japan Atomic Energy Society of Japan, Vol. 1, No. 4, pp. 352-360 (2002)
ReactorRecuperator
Precooler321MW
Turbine Compressor Generator
Efficiency 46%
RPV material is low cost alloy commonly used in LWR
Recuperator is compact heat exchanger with temperature efficiency 90 % jointly developed with MHI
Efficiencies of helium gas compressor over 90 % jointly developed with MHI
Outline of GTHTR300
X. Yan, et al., Cost and performance design approach for GTHTR300 power conversion system, Nucl. Eng. Des., 226, pp. 351-373 (2003)
Fluid Helium gas
Pressure Max. 1.0MPa
Temperature 30℃
Test conditions
1/3 scale model of helium gas compressor
Magnetic bearing
Magnetic bearing was developed, which supports
turbo-machine rotor without lubricants
Helium gas compressor with high efficiency
over 90% was developed for gas-turbine
Electro
magnet
Rotor blade
Rotor
Helium gas loop
R&D of components
X. Yan, et al., Aerodynamic Design, Model Test, and CFD analysisfor a Multistage Axial helium Compressor, ASME J. Turbomachinery, Vol. 130, (2008).
X. Yan, et al., DESIGN STUDY OF AIR COOLED GTHTR300A FOR INLAND INSTALLATION, PBNC 2012, PBNC 2012-0049, (2012).
HTTR
Heat utilization system
Chemical reactors
IHX
Reactor
Hot gas ductGas-turbine
HTTR-GT/H2 test (Plan)
H. Sato, et al., HTTR Demonstration Program for Nuclear Cogeneration of Hydrogen and Electricity, ICONE23-1459 (2015).
【GTHTR300 (275MWe x 4)】 【BWR-5 (1100MWe)】
★Volume : 674,000 m3
• Reactor building :354,000 m3
• Turbine building :320,000 m3
24 m
47 m
119 m
11 m
45 m
68.5 m
76 m
A
A
Reactor building Turbine building
A-A section
22 m
Ref) Figure is drawn from licensing document of Kashiwazaki-Kariya
power plant (No.3 unit)
93.7 m
★建屋容積:485,000 m3
109.2 m
84.0 m
★Volume:533,000 m3
Building volume is 79% of BWR-5
Turbine building
Smaller building volume
Ref) X. Yan, et al., Nuclear Eng. Design., 226,
p351-373 (2003)
80 m
53 m
0.0 0.5 1.0 1.5
LWR(PWR)
GTHTR300
Fuel cost (cents/kWh)
U purchase, conversion
enrichment
fabrication
storagereprocessing
waste disposal
MOX
0.0 0.5 1.0 1.5
LWR(PWR)
GTHTR300
Fuel cost (cents/kWh)
U purchase, conversion
enrichment
fabrication
storagereprocessing
waste disposal
MOX
Front-end process : U purchase, conversion/enrichment/fabrication
Back-end process : storage/reprocessing/waste disposal
Front-end process : Cost-up by high enrichment and coated fuel particle
Bask-end process : Cost-down by less amount of generated waste because of higher burn-
up and higher plant thermal efficiency
Fuel cost is the same as LWR because of high burnup and high thermal
efficiency despite that fabrication cost of coated fuel particles is higher.
Ref) Takei, et al., Trans. At. Energy Soc. Japan, Vol.5, No.2 (2006)
1.22 cents/kWh
1.23 cents/kWh
Competitive fuel cost
Development of high burn-up coated particle fuel in cooperation with NFIIrradiation test up to 100GWd/t (ISTC Regular Project)
Fuel compacts for irradiation test
Sandwich shuffling up to 120GWd/t
Refueling method and High Burn-up fuel
K. Kunitomi, et al., Design study on Gas Turbine High Temperature Reactor (GTHTR300), Trans. Japan Atomic Energy Society of Japan, Vol. 1, No. 4, pp. 352-360 (2002)
Suitable for Japanese fuel cycle policy
Available for existing reprocessing plant
Suitable for long-term temporary storage
Reprocessing plant
Power station
(LWR)
HTGR
Fuel cycle
Temporary storage
Decay heat removal
with natural
circulation of air
(without electricity)
Preprocessing
Ceramics fuel
block with high
corrosion resistance
Temporary storage
Reprocessing Spent fuel
Rotation
Extraction of
fuel particle
Fluidized
incinerator
Crushed fuel pin
Fuel particle
Fracture of
coating layer
Direct geological disposal *
* Accessible to policy of direct geological disposal
Reprocessing after temporary storage
Direct geological
disposal after
temporary storage
Maintenance technology developed using HTTR
Maintenance technology special to HTGRs Fuel handling technology ISI Helium purification, storage and supply system Reactivity control system Maintenance manual
Maintenance technology for future HTGRs Overhaul inspection of primary system Helium leak detection technology
Efficient maintenance works for general equipment Data base to establish condition based maintenance
Periodic inspection interval is 2 years. During inspection period, decay heat removal by SCS, refueling and inspection of system and components are carried out. Main critical work is the inspection of primary cooling system such as removal and exchange of turbo-machinery from PCV.
The critical path of maintenance is decay heat removal and inspection of primary cooling system. Maintenance works of systems for reactivity control, measuring and control, electric power, auxiliary system, ventilation and air conditioning are carried out using technologies developed for HTTR, which can be excluded from the critical paths.
Y. Shimazaki, et al, Development of maintenance technologies for the future high-temperature gas cooled reactor(HTGR) using operating experieces acquired in high-temperature engineering test reactor(HTTR) , J. Nuclear Sci., Technol., Vol. 51, Nos. 11-12, (2014)
HTGR can be constructed near consuming region due to higher safety features.
LWR can be constructed on the coast and
generated power is transmitted to the
consuming region.
Transmission distance 10 km
Construction cost of
transmission system* 1.9M$
Transmission distance 1,000 km
Construction cost of
transmission system* 193M$
* Source) Anpara Power Transmission System Project in India (Japan Bank for International Cooperation, Ex-post Evaluation Report on ODA Loan Projects 2006)
Total cost is 290M$. Total transmission distance is 1,508km. Estimated construction cost 0.19M$/km. Transmission line of 800kV is 409km. Transmission line of 400kV
is 1,099km, 550MW of power can be transmitted by 400kV line. Five transformer substations of 315MVA (400kV) are constructed and three substations are extended.
Low power transmission cost
A few percentage of reactor
construction cost of HTGR Almost same as reactor construction cost of LWR
By fully utilizing characteristics of HTGR; high heat efficiency, high performance to contain fission products and excellent inherent safety,
Costs of management for accident risks and additional safety measures are eliminated.Capital, operating and maintenance costs are reduced.
Unit【¥/kWh】
2.5 3.1 1.4 1.1
0.2 0.5
2.0 1.9 1.4 1.1
LWR*1
HTGR*2
Total: Over ¥8.9/kWh
Total: ¥6.4/kWh-2.4*1 Material 2 in website of Cabinet Secretariat: http://www.cas.go.jp/jp/seisaku/npu/policy09/archive02_hokoku.html
*2 JAEA estimation
■Operating and maintenance costs (¥-1.2/kWh)
Owing to fewer number of facilities in whole plant and less exposure to plant operators and workers as a result of retention of fission products inside fourfold coated fuel particles.
Compensation for damage, decommissioning of accident reactor, decontamination, etc.
■Cost of management for accident risks (¥-0.5/kWh)
■Expenses related to policy measuresLocation, disaster prevention, public relations, development of human resources, assessment and investigation, development of current/future technology for power generation, etc.
■Cost of Additional safety measures (¥-0.2/kWh)Emergency safety measures, emergency power generation facilities, reliability assurance of external power supply, measures for severe accidents, etc.
■Fuel cycle cost
■Capital cost (¥-0.5/kWh)
Owing to few number of water and steam system facilities, fewer number of facilities in whole plant and high heat efficiency of plant.
Comparison of cost with LWR
■Operation and maintenance costs (1.1)(Estimated by JAEA)
1.5
1.1
1.6
■Fuel cycle costs(1.5)(Estimated by JAEA in cooperation with NFI)
■Capital costs(1.6)( Estimated by JAEA in cooperation with nuclear industry )
U purchase・conversion:0.14, enrichment:0.29, fabrication:0.43*
reprocessing:0.40, Intermediate storage:0.02, waste disposal:0.18
Repair cost:0.41, expendable cost:0.45, Labor cost:0.19,
Business tax:0.05, business sharing expenses:0.01
Depreciable cost:1.02, Interest cost:0.24, Property
tax:0.11, Decommissioning cost:0.21
4.2Items Cost(Billion¥)
Reactor system[RPV, Reactor internal structure, reactivity control
system, fuel handling and storage system, VCS, etc.]
Power conversion system (Primary cooling system)
[Turbine, compressor, generator, PCV, HXV,
Heat exchanger, Hot duct, etc.]
Auxiliary system
[Systems of He purification, He storage & supply, cooling
water, ventilating and air conditioning and radiation control,
et al.〕
Electric system・Control & measuring system
Building and structure [R/B, HX/B for sharing]
17
14
7
6
11
合 計 55
*1)Takei, et al., Economical Evaluation on Gas Turbine High Temperature Reactor 300 (GTHTR300), Trans. Japan Atomic Energy Society of Japan, Vol. 5, No. 2, p.109-117, 2006.
Construction cost of GTHTR300
Based on the paper published in 2006(*1), construction cost for 1
plant of GTHTR300 is accounted by amount of components as 55B¥.
Power generation cost of HTGR(evaluated in 2006) Estimate condition
GTHTR300:4plants/Unit(600MWt/plant、275MWe/plant、1100MWe/Unit)
Average burn-up:120 GWd/t, Plant life:40 years, availability: 80%, Discounting rate:3% Effects of learning, line production and standardization of component and construction (Nth Plant), Modular concept
Construction cost includes those for design and fabrication of facility, plant construction and commissioning(Costs of R&D, licensing, land, site preparation, fuel and spares are excluded)
It should be noted that further R&D is necessary until actual power generation is achieved.
Power generation Cost
13
Availability80%
Note; Construction cost of the 1st plant cost 30% more. Further more, that of 1plant in 1 unit costs 10% more.
unit:¥/kWh
*:fabrication cost by facility satisfying safety requirements in 2006
HTGR
By fully utilizing characteristics of HTGR; high heat efficiency, high performance to contain fission products and excellent inherent safety, cost reduction is possible.
Power generation cost of HTGR(revised in 2011)
Cost of power generation
*2)Material 2 in website of Cabinet Secretariat: http://www.cas.go.jp/jp/seisaku/npu/policy09/archive02_hokoku.html
■Operation and maintenance costs(1.9~1.6*)
1.1
1.4
1.9~1.6
2.0
~1.7
■ Expenses related to policy measures (1.1)
■Fuel cycle costs (1.4)
■Capital cost(2.0~1.7*)
14
*1)Takei, et al., Economical Evaluation on Gas Turbine High Temperature Reactor 300 (GTHTR300), Trans. Atom. Ener. Soc. of Japan, Vol. 5, No. 2, p.109-117, 2006.
6.4~5.8*
Due to no experience of construction of demonstration plant and reprocessing of spent fuel, the cost of power
generation is estimated by JAEA, which was revised as that of 2011 under the postulated condition accounting for
the rates of increase and declining as same as those of LWR based on ¥4.2/kWh in the report (*1).
In the report (*2), costs of management for accident risks and additional safety measures are added to capital costs,
operation and maintenance costs, fuel cycle costs and expenses related to policy measures. However, costs of management for accident risks and additional safety measures are eliminated owing to the inherent safety design for
HTGRs. In case postulated as same as LWRs, they are set over ¥0.5/kWh and ¥0.2/kWh, respectively. Hence, this
evaluation can not be compared with that of LWR unconditionally. It should be also noted that more R&D is necessary before actual power
generation is realized.
• Due to lower power density, construction cost of reactor system is higher
• Construction cost except for reactor system is lower due to following reasons Significant fewer number of water and steam system facilities than LWR Fewer number of electric and measuring system and their capacity No reactor containing vessel, and the volume of reactor building is
smaller than LWR
• Owing to high enriched coated particle fuel, costs for processes for enrichment, conversion and fabrication are high
• Owing to higher burn-up, amount of spent fuel is small. Owing to higher thermal efficiency, costs of reprocessing and waste disposal is low.
• Owing to fewer number of facilities and amount of components in whole plant, maintenance cost is lower
• Owing to higher thermal efficiency, the cost is totally lower
Availability70~80%
unit:¥/kWh
Postulated same increase rate as that of LWR in report(*2)
*: Left value: availability 70% (As same as that of LWR in report(*2))
Right value: availability 80%(as same as that of 2006 version)
**:Discounting rate:3%
Postulated as same as that of LWR in report(*2)No change in cost for Siting, Disaster prevention, public relations, development of human resources, assessment and investigation, development of current/future technology for power generation, etc.
HTGR
Postulated same increase rate as that of LWR in report(*2)
Postulated same declining rate as that of LWR in report(*2)
R&D Subjects
(1) Design study
(2) Safety demonstration
test under sever
conditions
(3) Irradiation tests of fuel
and graphite
(4) Life-extension of
graphite
(5) Verification of codes
(6) Next step of IS process
for hydrogen production
(7) Helium gas turbine
(8) HTTR operation and
maintenance
R&D subjects
15