0
Technology Reviews

HTR-TN Achievements and Prospects for Future Developments

[+] Author and Article Information
Dominique Hittner

 AREVA NP, Tour AREVA, 92084 Paris-la-Défense Cedex, France

Carmen Angulo

 Suez Tractebel, 7, Avenue Ariane, 1200 Brussels, Belgium

Virginie Basini

 CEA/Cadarache, 13108 Saint Paul-lez-Durance Cedex, France

Edgar Bogusch

 AREVA NP, Paul-Gossen-Strasse 100, 91052 Erlangen, Germany

Eric Breuil, Denis Verrier

 AREVA NP, 10, rue Juliette Récamier, 69006 Lyon, France

Derek Buckthorpe

 AMEC, Booths Park, Chelford Road, Knutsford WA16 8QZ, UK

Vincent Chauvet

 LGI Consulting, 37, rue de la Grange aux Belles, 75010 Paris, France

Michael A. Fütterer

 JRC/IE, P.O. Box 2, 1755 ZG Petten, The Netherlands

Aliki van Heek

 NRG, P.O. Box 25, 1755 ZG Petten, The Netherlands

Werner von Lensa

 FZJ, 52428 Jülich, Germany

Pascal Yvon

 CEA/Saclay, 91191 Gif/Yvette, France

J. Eng. Gas Turbines Power 133(6), 064001 (Feb 14, 2011) (9 pages) doi:10.1115/1.4000799 History: Received November 28, 2008; Revised February 23, 2009; Published February 14, 2011; Online February 14, 2011

It is already 10 years since the (European) High Temperature Reactor Technology Network (HTR-TN) launched a program for development of HTR technology, which expanded through three successive Euratom framework programs, with many projects in line with the network strategy. Widely relying in the beginning on the legacy of the former European HTR developments (DRAGON, AVR, THTR, etc.) that it contributed to safeguard, this program led to advances in HTR/VHTR technologies and produced significant results, which can contribute to the international cooperation through Euratom involvement in the Generation IV International Forum (GIF). the main achievements of the European program, performed in complement to efforts made in several European countries and other GIF partners, are presented: they concern the validation of computer codes (reactor physics, as well as system transient analysis from normal operation to air ingress accident and fuel performance in normal and accident conditions), materials (metallic materials for vessel, direct cycle turbines and intermediate heat exchanger, graphite, etc.), component development, fuel manufacturing and irradiation behavior, and specific HTR waste management (fuel and graphite). Key experiments have been performed or are still ongoing, like irradiation of graphite and of fuel material (PYCASSO experiment), high burn-up fuel PIE, safety test and isotopic analysis, IHX mock-up thermohydraulic test in helium atmosphere, air ingress experiment for a block type core, etc. Now HTR-TN partners consider that it is time for Europe to go a step forward toward industrial demonstration. In line with the orientations of the “Strategic Energy Technology Plan (SET-Plan)” recently issued by the European Commission that promotes a strategy for development of low-carbon energy technologies and mentions Generation IV nuclear systems as part of key technologies, HTR-TN proposes to launch a program for extending the contribution of nuclear energy to industrial process heat applications addressing (1) the development of a flexible HTR that can be coupled to many different process heat and cogeneration applications with very versatile requirements, (2) the development of coupling technologies for such coupling, (3) the possible adaptations of process heat applications required for nuclear coupling, and (4) the integration and optimization of the whole coupled system. As a preliminary step for this ambitious program, HTR-TN endeavors to create a strategic partnership between nuclear industry and R&D and process heat user industries.

Copyright © 2011 by American Society of Mechanical Engineers
Your Session has timed out. Please sign back in to continue.

References

Figures

Grahic Jump Location
Figure 1

Coated particle fabrication, CVD coating furnace (CEA Cadarache)

Grahic Jump Location
Figure 2

Compact fabrication, compacting press (CERCA Romans)

Grahic Jump Location
Figure 3

R/B measurements versus burn-up from the HFR-EU1bis test

Grahic Jump Location
Figure 4

Modeling the amoeba effect with the ATLAS code

Grahic Jump Location
Figure 5

Ceramographic cross sections of Belgonucléaire Pu coated particles

Grahic Jump Location
Figure 6

CLAIRE loop, air (CEA Grenoble)

Grahic Jump Location
Figure 7

HE-FUS 3 loop, helium (ENEA, Brasimone)

Grahic Jump Location
Figure 8

Domains of INNOGRAPH irradiations

Grahic Jump Location
Figure 9

Relative volume change in different graphite grades with neutron dose

Grahic Jump Location
Figure 10

Draft mapping of graphite irradiations by GIF partners

Grahic Jump Location
Figure 11

UJV Rĕz in a reactor corrosion loop

Grahic Jump Location
Figure 12

Fuel waste management routes

Grahic Jump Location
Figure 13

Disintegration of a compact by pulsed currents

Grahic Jump Location
Figure 14

TRISO particle embedded in glass (left) and SiC

Grahic Jump Location
Figure 15

Graphite decontamination process

Tables

Errata

Discussions

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In