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
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Disintegration of a compact by pulsed currents

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TRISO particle embedded in glass (left) and SiC

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Graphite decontamination process

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Figure 1

Coated particle fabrication, CVD coating furnace (CEA Cadarache)

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Figure 2

Compact fabrication, compacting press (CERCA Romans)

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Figure 3

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

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Modeling the amoeba effect with the ATLAS code

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Ceramographic cross sections of Belgonucléaire Pu coated particles

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CLAIRE loop, air (CEA Grenoble)

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

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Domains of INNOGRAPH irradiations

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Relative volume change in different graphite grades with neutron dose

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Draft mapping of graphite irradiations by GIF partners

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UJV Rĕz in a reactor corrosion loop

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Figure 12

Fuel waste management routes



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