Research and Prospect for Sustainable Nuclear Energy ...
Transcript of Research and Prospect for Sustainable Nuclear Energy ...
Research and Prospect for
Sustainable Nuclear Energy Utilization
in Japan
Kazufumi TSUJIMOTOPartitioning and Transmutation Technology Division
Nuclear Science and Engineering Center
Japan Atomic Energy Agency (JAEA)
4th Workshop Energy for Sustainable Science at Research Infrastructures, 23-24 Nov., 2017, Magurele, Romania
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Contents
Nuclear power in Japan
The 4th Strategic Energy Plan in Japan
Outlook for future
Prospect and research for utilization of nuclear power
Current situation of nuclear power plant
Current situation and R&D on nuclear fuel cycle
R&D on Partitioning and Transmutation (P&T)
Summary
Growing Interest in Energy Issues
3Source:TEPCOSource:NYT
The Great East Japan Earthquake and the Fukushima Daiichi accident
Many thermal power plants, as well as nuclear power plants, were damaged,
and severe electricity shortage occurred in 2011.
Domestic and international situation of the development and utilization of
nuclear energy was drastically changed.
In Japan, the operation of the nuclear power plant is almost led to the situation
of zero.
Electricity Generation by Source in Japan
4
Japan depends on fossil fuels, oil/coal/natural gas (LNG), imported from abroad.
Dependency increased to 88% (based on the composition of power sources in
FY2014, more than during the first oil crisis.
Primary energy self-sufficiency of major countries (2014) and trend of Japan’s composition of energy
sources to generate electricity (source : “JAPAN’s ENERGY 2016 edition” METI)
Electricity Generation by Source in Japan
5Source : Japan Atomic Energy Relations Organization
The 4th Strategic Energy Plan of Japan
6
On April 11, 2014, the Cabinet decided to approve the new Strategic Energy Plan
as the basis for the orientation of Japan’s new energy policy, considering the
dramatic changes in energy environments inside and outside Japan.
This plan gives a direction of Japan’s energy policies for medium/long-term
(about next 20 years). It declares a period from now to 2008-2020 should be a
special stage to reform a variety of energy system.
Safety
SelfSufficiency
Energy Security
Further exceeds before the earthquake
(approximately 20%)
ElectricPowerCost
Economic Efficiency
Reducing more than present costs
CO2
Emission
Environment Suitability
Achieving reduction targets of greenhouse gas
that are comparable to Western countries
Safety always
comes first !
Principles of the Strategic Energy Plan (1/2)
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NuclearImportant base-load power source as low carbon and quasi-domestic energy
source, contributing to stability of energy supply-demand structure, on the
major premise of ensuring of its safety, because of the perspectives;
Superiority in stability of energy supply and efficiency,
Low and stable operation cost, and
Free from GHG emission during operation.
Direct and indirect GHG emission for different sources of electricity
(“Nuclear Energy:Combating Climate Change”, OECD/NEA(2105))
However, dependency on nuclear power generation will be lowered to the
extent possible by thorough energy saving and maximum introduction of
renewable energy as well as improving the efficiency of thermal power
generation.
Principles of the Strategic Energy Plan (2/2)
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Renewable (solar, wind, geothermal, hydroelectricity, biomass)Promising, multi-characteristic, and important energy source with low carbon
and domestic energy sources
Accelerating their introduction as far as possible for three years, and then keep
expanding renewables
OilImportant energy source as both an energy resource and a raw material,
especially for the transportation and civilian sectors, as well as a peaking
power source
Natural GasImportant energy as a main intermediate power source, expanding its roles in
a variety of fields
CoalRevaluating as an important base-load power source in terms of stability and
cost effectiveness, which will be utilized while reducing environmental load
Constitution of Electric Power Supply
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There is no energy source which has strengths from every aspect in terms of
stability, cost, environmental burden. Realistic and balanced demand-supply
structure will be developed based on each energy source.
Source : Strategic Energy Plan
Targets in order to achieve 3E+S
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Self Sufficiency
Currently at 6%
【Target】
Self-sufficiency rate of 25%
(20% before 2011)
Electric Power Cost
Increase in electricity prices
after 2011
(Industrial=30%, Residential=20%)
【Target】
Reduce electric power cost
to 2013 level or less
CO2 Emission
【Target】
In FY2030, achieving -26%
compared to FY 2013
(Paris Agreement)
2013 CO2 emission worst on record※ from fuel combustion only
SA
FE
TY
Energy security
Economy
Environment
Source : the Long-term Energy Supply and Demand Outlook Subcommittee, Advisory Committee for Natural Resources and Energy
Prospect of Power Source Mix
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CO2 emissions
2013 2030
CO2 kg/kwh 0.570 0.370 -34%
Total (Gt) 1.408 1.042 -26%
The ideal compositions of power source in the future (FY2030) that will be
realized when implementing policies in order to achieve 3E+S based on the
Strategic Energy Plan.
source : “JAPAN’s ENERGY 2016 edition” METI)
Restart of Suspended Nuclear Power Plant
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Before march 2011, 54 units (48.8GWe)
were operated in Japan.
After March 2011, 6 units excluding
Fukushima Daiichi 6 units were decided
to be decommissioned.
Nuclear Regulatory Authority (NRA) was
newly established on 2012 and new
safety regulations were issued by NRA.
NRA approved basic design of 12 units,
and 14 units are under review. Five units
are operated at present.
http://www.genanshin.jp/english/index.html
Issues for Nuclear in Strategic Energy Plan
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Steady approach for key issues to be solved without putting
off implementing measures into the future
(1) Nuclear fuel cycle The basic policy of Japan is to promote a nuclear fuel cycle that
reprocesses spent fuels and effectively utilizes the plutonium retrieved,
from the viewpoint of effective utilization of resources and reduction of
the volume and harmfulness of high-level radioactive waste.
(2) Spent fuel management
Drastic reinforcement of measures for final disposal of high-level
radioactive waste
“GOJ will promote technology development on volume reduction
and mitigation of degree of harmfulness of radioactive waste.
Specifically, development of technologies (snip) including nuclear
transmutation technology using fast reactors and accelerators, will
be promoted by utilizing global networks for cooperation.”
Nuclear Fuel Cycle in Japan
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Vitrified Waste
Storage CenterLow-Level Radioactive
Waste Disposal Center
Sub-surfaced
disposal test cavern
Next
Reprocessing
plant
Fast
Reactor
(FR)
Storing : approx. 2,900tU
Storage capacity : 3,000tU
Storing :
approx. 14,000tU
Storage capacity :
approx. 20,000tU
Off-site storage facility(Spent Fuel Interim Storage)
Mutsu:5,000tU
(Constructed : 2013)
MOX Fuel
Fabrication Plant
Nuclear
Power
Plant(Spent Fuel Pool
etc.)
Rokkasho
Reprocessing Plant
Waste (from
Spent Fuel
Reprocessing)
returned from
UK and France
Waste from operation
and decommissioning
Geological disposal
repository
Spent Fuel
MOX Fuel
R&Ds of FR Fuel Cycle in JAEA
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Fuel Fabrication
FR
Evaluation of volume
reduction, etc. by
utilization of FR cycle Fuel Fabrication: Remote MA-bearing
MOX fuel fabrication technology
Determination of fuel composition range applicable
Reactor Characteristics
& Reactor system: Feasibility confirmation of FR plant
technologies Acquisition of characteristics of MA-
containing core
Fuel Development &
Irradiation Test: Systematic irradiation tests
of MA-bearing MOX fuel, High Pu-contents MOX fuel
Spent
MOX fuel
Monju
Joyo
Pu-3
CPF
Reprocessing
Reprocessing: Development of MA partitioning
process and performance evaluation Establishment of feasible process concepts
Comprehensive system evaluation: Integration of information in each area &
narrowing prospective system concepts Verification of effects on reduction of the
volume and radiotoxicity of radioactive wastes
AGFFMF
U, Pu, MA
MA-bearing
new MOX fuel
Partitioning and Transmutation (P&T)
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MA (Np,Am,Cm)
Dominant to the potential toxicity in long
term(~107 years)
Heat from 241Am (T1/2=432yr) prevents
compact disposal.
Transmutation
Sr, Cs : 90Sr and 137Cs (T1/2~30yr) are major
heat sources which is very important factor in
determining the repository scale.
After appropriate cooling, compact
disposal is possible
PGM (Ru,Rh,Pd,Tc) : Difficult to be solidified
in the glass
Utilization as the rare metal
Other FP : Rare earths are less radioactive
and able to be highly loaded in the glass
Rational disposal (Compact layout)
Reprocess
High level liquid waste
MA, FP(Sr-Cs,
PGMs, REs)
Ag-I
(Iodine)
Hull & end-
piece
TRU wastes
Glass
solidification
Underground
disposal
Cement
solidification
Underground disposal
(Compact layout)
50 years
storage
To be smart disposal !Small long-term risk
Compact repository
Compre-
ssion
Present waste management
Reduction of Potential Toxicity by P&T
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Radio-toxicity can be
reduced by 2 orders, if
99.5% transmutation is
achieved.
The time period to reduce
the radio-toxicity below the
level of natural uranium
used as raw material:
10,000y 500y
103
104
105
106
107
108
109
1010
1011
101 102 103 104 105 106 107
使用済み燃料毒性高レベル廃棄物毒性分離変換導入時毒性天然ウラン毒性(9t、娘核種を含む)
経口摂取に係る放射性毒性(ALI)
経過年
Spent fuel
HLW without Transmutation
99.5% Transmutation for MA
Natural Uranium (9 ton)
Time after reprocessing (Year)
Po
ten
tia
l to
xic
ity o
f 1
tU s
pe
nt fu
el (B
q/A
LI)
Reduction of Repository Area by P&T
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MA Transmutation
MA Transmutation
+
FP Partitioning
+
Long-term storage of
Sr-Cs calcined waste
Vitrified waste:8,300cans
(CT:45y, Area:0.01km2)
Sr-Cs calcined waste:5,100cans
(CT:320y, Area:0.005km2)
Repository area can be reduced to 1%, if
320 years storage can be acceptable for
Sr-Cs waste.
Vitrified waste:8,300cans
(CT:5y, Area:0.18km2)
Separation of Am-241 allows closer
configuration
Sr-Cs calcined waste:5,100cans
(CT:130y, Area:0.23km2)
Vitrified HLW:40,000 cans
(CT:50y, Area:1.8km2)
TRU waste(0.13km2)Non PT
1.8 km2
0.41 km2
0.015 km2
waste volume per 32,000 HMt of 4-year cooled 45GWd/HMt
LWR spent fuel (=40 years operation of 40GWe generation)
Fuel Cycle Concept for P&T in JAEA
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FR
Fuel fabricationFR
FR
U, Pu, MA
Reprocessing
HLW
Geological disposal
Commercial FBR Fuel Cycle
FRFR
Fuel fabricationFRFR
FRFR
U, Pu, MA
Reprocessing
HLW
Geological disposal
Commercial FBR Fuel Cycle
Geological disposal
Transmutation Cycle
Commercial Fuel Cycle
Fuel fabrication Reprocessing
Partitioning
U, Pu
I-129
MA, LLFP
PartitioningFuel fabrication
MA, LLFP
HLW (MA, FP)
Dedicated transmuter
FR
LWR
LWR
Geological disposal
Transmutation Cycle
Commercial Fuel Cycle
Fuel fabrication Reprocessing
Partitioning
U, Pu
I-129
MA, LLFP
PartitioningFuel fabrication
MA, LLFP
HLW (MA, FP)
Dedicated transmuter
FRFR
LWR
LWR
Homogeneous cycle Double-Strata (ADS)
・Dedicated (second) transmutation fuel cycle
with Accelerator-Driven System (ADS) is
added to commercial fuel cycle.
・MA recovered from commercial fuel cycle is
confined in the compact transmutation cycle.
・The ADS fuel mainly consists of MA (>50%).
・MA is recycled in the next-generation
reprocessing plant.
・MA transmutation is performed in
all electricity generating FR plant.
・MA is homogeneously mixed to FBR
fuel with small amount up to 5 wt.%.
P&T technology is expected to be effective to mitigate the burden of the HLW
disposal by reducing the radiological toxicity and heat generation.
Conceptual Design of ADS in JAEA
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ガードベッセル
炉心支持構造物
ビーム窓
原子炉容器
炉心槽
主循環ポンプ
ビームダクト
内 筒
蒸気発生器
Guard Vessel
Inner tube
Beam Duct
Window
Core Vessel
Core Support
Steam
GeneratorMain Pump
Support
Structure
• Proton beam : 1.5GeV ~30MW
• Spallation target : LBE
• Coolant : LBE
• Subcriticality : keff = 0.97
• Thermal output : 800MWt
• Core height : 1000mm
• Core diameter : 2440 mm
• Fuel inventory : 4.2t (MA:2.5t)
• Fuel composition :
(MA + Pu)N+ZrN (Mono-nitride)
Inner : 70%MA+30%Pu
Outer : 54%MA+42%Pu
• Transmutation rate :
250kg(MA) / 300EFPDK. Tsujimoto, H.Oigawa, K.Kikuchi, et. al, “Feasibility of Lead-Bismuth-
Cooled accelerator-Driven System for Minor-Actinide Transmutation”,
Nucl. Tech. 161, 315-328 (2008).
Purpose : MA transmutation
Energy Balance of ADS
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Characteristics of ADS:•Chain reactions stop when the accelerator is
turned off.
•LBE is chemically stable.
High safety can be expected.
•High MA-bearing fuel can be used.
MA from 10 LWRs can be transmuted.
Proton beam
MA-fueled LBE-
cooled subcritical
core
Power generation
To accelerator
To grid Spallation target
(LBE)
Super-conducting LINAC
Fission energy
Spallation target
Proton
Long-lived
nuclides (MA)
Short-lived or stable
nuclides
Fast neutrons
Utilizing chain reactions in
subcritical state
Fission neutrons
Transmutation by ADS
Max.30MW
800MW
100MW
170MW
270MWMA: Minor Actinides
LBE: Lead-Bismuth Eutectic
Technical Issues of ADS
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Reactor structure
Beam window
Spallation target
LBE handling
Accelerator
SC Linac
High power
Reliability
MA-loaded
subcritical core
Nuclear design
Reactor physics
Fuel cycle
Partitioning
MA-bearing Fuel
fabrication
Dry reprocessing
Validation of codes
and nuclear data
Reactor physics of
subcritical (k-eff
measurement, etc.)
Corrosion of
material
Test of equipment
in cold LBE loop
Oxygen control
Operation of J-
PARC LINAC
Experiment in KUCALBE loop in JAEA
LINAC in J-PARCJ-PARC:Japan Proton
Accelerator Research Complex
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R&D for Superconducting Accelerator
Mockup of cryomodule (2 superconducting cavities)
was fabricated and tested. The design study
provided that the SC-LINAC consisting of 89
cryomodules and the length was estimated as
472m.
The accumulation of operating experience of the
LINAC (400MeV, 25Hz) in J-PARC will contribute
the improvement of the reliability.
Mockup of Cryomodule
Proton Linac (400MeV) in J-PARC
Ion source
CW beam
RF
RFQ DTL
70 keV 2 MeV
0m 5m ~15m 110m
1.5 GeV100 MeV~10 MeV
Superconducting part
Liquid He
RF RF RF RF RF
Cryomodule
472 m
Superconducting cavity
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R&D for Lead-Bismuth Eutectic (LBE)
Oxygen Sensor Calibration Device
– To prevent corrosion by flowing LBE, oxygen potential in
LBE should be controlled in appropriate potential range.
– Development of oxygen potential sensor and loop tests for
oxygen potential control mechanism are underway.
OLLOCHI (Oxygen-controlled Lbe LOop for Corrosion
tests in HIgh temperature)
– Material corrosion database for various temperature, oxygen
potential, LBE flow rate will be collected.
– The loop is operated from this April.
IMMORTAL (Integrated Multi-functional MOckup for
TEF-T Real-scale TArget Loop)
– Purpose of experiments is demonstration of safe operation of
LBE loop by reflecting operation condition of J-PARC LBE
Spallation target.
R&D for Reactor physics of ADS
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Collaboration study with Kyoto University using KUCA (Kyoto University
Critical Assembly).
14 MeV neutron : D + T traget
Spallation neutron : 100 MeV proton + W target
Core image to simulate ADS in
KUCA
F F F F F
F F F F F
F F ' F ' F ' F
F F ' F ' F ' F
F F ' F ' F
F F F F
F F F F
F F F F
F F F F
F F F F
16 16
Proton beams
C2S6
C1 S4
S5 C3
KUCA core
Pulsed neutron generator FFAG accelerator
Beam line of D
D + T target =
14 MeV neutrons
100 MeV protons + W target
= Spallation neutrons
Beam line of protons
W target
Ttarget
Kyoto University Critical Assembly (KUCA) and Fixed-Field
Alternating Gradient (FFAG) accelerator
Hadron Experimental Facility
30 GeV SynchrotronMaterials and Life Science Experimental
Facility
3 GeV Synchrotron
400 MeV
LINAC
To neutrino
detector
Site for Transmutation
Experimental Facility
Future R&D Plan in J-PARC:
Transmutation Experimental Facility (TEF)
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Critical Assembly
Pb-Bi Target
Transmutation Physics
Experimental Facility: TEF-P
ADS Target Test
Facility: TEF-T
Proton Beam
Multi-purpose
Irradiation Area
Transmutation Experimental
Facility (TEF) consists of
Transmutation Physics
Experimental Facility (TEF-P) and
ADS Target Test Facility (TEF-T)
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Summary
Nuclear utilization in Japan (“Strategic Energy Plan”, Apr. 2014)
“Nuclear power is an important base-load power source”
“GOJ will promote development of technologies for reducing the
volume and harmfulness of radioactive waste in order to secure a wide
range of options in the future.”
Motivation of the R&D activities on P&T technology
Steady implementation of High Level Waste (HLW) disposal is one of the most important issues.
Partitioning and Transmutation (P&T) will be a key technology to reduce the environmental burden of HLW.
JAEA’s current status and future plan for MA transmutation technology with ADS
JAEA has been promoted R&D activities on P&T technology based on two concepts, FR and ADS.
Various basic R&D have been implemented, and new experimental facility, TEF, is proposed in the J-PARC.