High temperature Industrial nuclear cogeneration · PDF filetemperature nuclear cogeneration by ... the nuclear plant ... Arcelor Mittal Poland S.A. 8 1273

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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

4

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

11

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

12

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)