Graphite irradiation testing for HTR technology at the High Flux Reactor in Petten

Journal of Nuclear Materials

Volumn 381, Issue 1-2, 2008, Pages 68-75

  Vreeling, J A ^a   Wouters, O ^a   Laan, J G van der ^a  

^a NUCLEAR RESEARCH AND CONSULTANCY GROUP NRG   (Netherlands)

Author keywords

[No Author keywords available]

Indexed keywords

CARBON; EXPERIMENTS; GRAPHITE; HIGH TEMPERATURE REACTORS; IRRADIATION; RESEARCH REACTORS; THERMAL EXPANSION; THERMAL SPRAYING; THERMOELECTRICITY;

COEFFICIENT OF THERMAL EXPANSIONS; DESIGN CURVES; DIMENSIONAL CHANGES; DYNAMIC YOUNG'S MODULUS; EUROPEAN; FRAMEWORK PROGRAMMES; HIGH FLUX REACTORS; HIGH-TEMPERATURE; IRRADIATION EXPERIMENTS; IRRADIATION TEMPERATURES; NUCLEAR RESEARCHES;

RADIATION;

EID: 54149119120     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2008.07.041     Document Type: Article

References (12)

1. D.E. Buckthorpe et al., Materials for the High Temperature Reactor, in: HTR2002 Conference, Petten, The Netherlands, 2002.
2. D.E. Buckthorpe et al., Research and Development Programme on HTR Materials, in: ICAPP03 Conference, Cordoba, Spain, 2003.
3. D.E. Buckthorpe et al., RAPHAEL Project: Materials Development for the VHTR - Results From HTR-M & HTR-M1 Projects Plus Future RAPHAEL Programme, in: HTR2006 Conference, South Africa, 2006.
4. In: Nightingale R.E. (Ed). Nuclear Graphite (1962), Academic Press, New York
5. Simmons J.H.W. Irradiation Damage in Graphite (1965), Pergamon, Oxford
6. Reynolds W.N. The Physical Properties of Graphite (1968), Elsevier, Amsterdam
7. Kelly B.T. Physics of Graphite (1981), Applied Science Publishers, London
8. J.I. Wolters, Innovative Graphites (INNOGRAPH,253-01), Neutron Metrology in the HFR, Internal NRG Report K5079/05.70730/I, Petten, 2005.
9. S. de Groot, INNOGRAPH-post cycle-01 Thermomechanical Analyses, Internal NRG Report 20787/04.59025/I, Petten, 2004.
10. E.R. Meurs, INNOGRAPH-1A Post Test, Internal NRG Note, Petten, 2005.
11. B.J. Marsden et al., Dimensional and material property changes to irradiated gilsocarbon graphite irradiated between 650 and 750 °C, J. Nucl. Mater., these proceedings.
12. ASTM C 781-96, Standard practice for testing graphite and boronated graphite components for high, Temperature Gas-cooled Nuclear Reactors, 1996.