high temperature industrial nuclear cogeneration · pdf filetemperature nuclear cogeneration...
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NC2I is one of SNETP’s strategic technological pillars, mandated to coordinate the
demonstration of high temperature nuclear cogeneration.
www.snetp.eu
High temperature
Industrial nuclear cogeneration
Dominique HITTNER
1
© OECD/IEA 2016
From 2 degrees to “well-below 2 degrees”
Industry and transport accounted for 45% of direct CO2 emissions in 2013, but they are responsible for 75% of the remaining emissions in the 2DS in
2050.
Energy- and process-related CO2 emissions by sector in the 2DS
Source: Energy Technology Perspectives, 2016
0
10
20
30
40
2013 2020 2030 2040 2050
Transport
Industry
Agriculture
Buildings
Other transformation
Power
Gt
CO
2
2
Modular HTGR meets industrial heat market needs
▶ High temperature
3
European industrial heat demand
Industrial steam
distribution networks
✚ Industrial maturity
✚Enhanced safety due to intrinsic safety concept
✚Modular HTGRs are SMRs
Maturity of HTGR technology
▶ Already significant experience: test reactors and industrial prototypes
▶ Now an industrial prototype in construction in China, commissioning expected in 2018
▶ Plans for demonstration of high temperature nuclear cogeneration by the PRIME consortium (NC2I, NGNP Industry Alliance, JAEA, KAERI) ↳ Project of demonstration on a Polish
industrial site
⇒ Deployment possible by ~ 2030.
Demonstration in industrial environment is the condition for getting HTGR cogen. systems to the market place
✚ Potential for further developments HTGR cogeneration beyond steam networks First step towards VHTR
Extended market in the longer term
DRAGON, U.K. 20 MW, 1963-76
AVR, Germany
15 MWe, 1967-88
HTR-10, China
10 MWth, since 2000
Peach Bottom, US 200 MWth, 1967-74
HTTR, Japan
30 MWth, since 1998
THTR, Germany
300 MWe,1986-89
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Fort Saint-Vrain, US
300 MWe, 1976-89
HTR-PM, China (2 x 106 MWe) March 2016 (Image: CNEC)
Intrinsic safety of modular HTGR
▶ Safety based on simple phenomena (conduction, radiative heat transfer), no need of engineered active or passive dedicated safety systems ⇒easy to demonstrate
▶ Core melting excluded
▶ No radioactive release outside the nuclear plant
▶ Proven by safety tests on actual reactors
⇒Location close to industrial applications acceptable
⇒Simplified safety design: a path for competitiveness
5
Measured core temperatures in HTR-10
after a helium circulator trip test
MHTGR Fuel Temperatures with Passive Heat
Removal During Loss of Forced Cooling
Industrial cogeneration requires limited power
▶ The power of modular HTGRs
≲600 MWth fits with
industrial needs
▶ The example of
Poland
13 largest chemical plants need 6500 MW of heat at T=400-550°C
They use 200 TJ / year, equivalent to burning of >5 Mt of natural gas or oil
Replacing by HTGR would reduce CO2 emission by 14-17 Mt / year
6 6 6
6
Plant boilers MW
ZE PKN Orlen S.A.Płock 8 2140
Arcelor Mittal Poland S.A. 8 1273
Zakłady Azotowe "Puławy" S.A. 5 850
Zakłady Azotowe ANWIL SA 3 580
Zakłady Chemiczne "Police" S.A. 8 566
Energetyka Dwory 5 538
International Paper - Kwidzyn 5 538
Grupa LOTOS S.A. Gdańsk 4 518
ZAK S.A. Kędzierzyn 6 474
Zakl. Azotowe w Tarnowie Moscicach S.A. 4 430
MICHELIN POLSKA S.A. 9 384
PCC Rokita SA 7 368
MONDI ŚWIECIE S.A. 3 313
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NC2I is one of SNETP’s strategic technological pillars, mandated to coordinate the
demonstration of high temperature nuclear cogeneration.
www.snetp.eu
Back-up slides
7
Nuclear energy nearly absent from non-electricity energy
European electricity consumption European heat consumption
(Source: Eurostat)
8 8
What are the conditions for enabling cogeneration HTGR deployment?
▶ No significant technical obstacle
▶ Major challenges: to show
Feasibility of licensing: acceptability by regulators of
• The specific safety approach of modular reactors
• The coupling with industrial processes
Economic competitiveness
Adaptability to industrial needs (availability, reliability,
flexibility)
⇒Need for industrial demonstration of the coupling
9 9
10 + Recent commitment of chemical industry
On 14//2/17 the government
issued the final version of its
“Strategy for responsible
development” including a
plan for HTR deployment for
industrial cogeneration
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Fuel cycle and waste management (1)
▶ Fuel and graphite cycle feasibility issues
Fuel conditioning and disposal (more or less separated from graphite)
Graphite decontamination
Graphite/particle separation
Kernel separation
Fuel recycling • Fabrication of
actinide fuel
• HTR cores with actinides
• Sustainability: fuel cycle scenarios
Graphite recycling
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Used fuel
Fuel block dismantling
Compact
conditioning &
disposal
Graphite
decontaminationGraphite/particle
separation
Direct fuel
conditioning
& disposalBlocscompacts
Particles Graphite Graphite
conditioning
& disposal
Graphite
recycling
Kernel separation Particle
conditioning
& disposal
Reprocessing/recycling
route
D ROUTE C ROUTE B ROUTE A ROUTE
+ Graphite separate management
Fuel cycle and waste management (2)
▶ Fuel behaviour in disposal conditions:
leaching tests
⇒Robustness of coated particles comparable to vitrified wastes
▶ Fuel conditioning
▶ Graphite decontamination
▶ Graphite / particle & kernel separation
▶ Fabrication of actinide fuel
▶ Cores with actinides
Feasibility of core 100% loaded with Pu from LWRs
Very efficient Pu burning • Only 15% of initial Pu left
• The Pu left has a low fissile content (20%)
▶ Fuel cycle scenarios with U/Pu or Th/233U cycles
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Electric pulse generator
Water
Before processing After processing
Disintegration of a compact by pulsed currents
Graphite with
radioactive
contamination
gasification
CO + H2
+ H2O
+ heat Radionuclides
remain as solid
residue*
Solid
carbonreduction
+
* Except volatile radionuclideslike 36Cl, T and 14C
Mass of actinides as fraction of initial Pu mass
Bu (Gwd/tHM)
Pu Cm Am U Np
0 1
760 0.1457 0.0486 0.0397 0.0007 0.0001
Pu vectors as fraction of initial Pu mass Bu
(Gwd/tHM)
238Pu 239Pu 240Pu 241Pu 242Pu
0 0.0259 0.5385 0.2366 0.1313 0.0678
760 0.0160 0.0019 0.0070 0.0054 0.1155
TRISO particle embedded in glass (left) and SiC (right)