Results 11 to 20 of about 564 (77)

Influence of thermal treatment at various temperatures on structure and radiation-induced effects in advanced ceramic breeder pebbles

Nuclear Materials and Energy
Advanced ceramic breeder (ACB) pebbles consisting of 65 mol% lithium orthosilicate (Li4SiO4) and 35 mol% lithium metatitanate (Li2TiO3) are currently being developed as the European Union’s reference material for tritium breeding in future thermonuclear ...
A. Ansone, A. Antuzevics, L. Avotina, E. Sprugis, A. Trimdale-Deksne, J.M. Leys, R. Knitter, A. Zarins   +7 more
doaj   +3 more sources

Fusion Materials Development at Forschungszentrum Jülich

Advanced Engineering Materials, Volume 22, Issue 6, June 2020., 2020
In fusion material research, the focus has been twofold‐plasma facing and structural materials allowing to withstand the extreme conditions such as neutron bombardment and high heat fluxes. In this contribution, the background for the choice of tungsten as first wall material is given and the advanced materials developed at Forschungszentrum Jülich ...
Jan Willem Coenen
wiley   +1 more source

Compilation of Existing Neutron Screen Technology

Science and Technology of Nuclear Installations, Volume 2014, Issue 1, 2014., 2014
The presence of fast neutron spectra in new reactors is expected to induce a strong impact on the contained materials, including structural materials, nuclear fuels, neutron reflecting materials, and tritium breeding materials. Therefore, introduction of these reactors into operation will require extensive testing of their components, which must be ...
N. Chrysanthopoulou, P. Savva, M. Varvayanni, N. Catsaros, Alejandro Clausse   +4 more
wiley   +1 more source

Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities

Science and Technology of Nuclear Installations, Volume 2013, Issue 1, 2013., 2013
The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessing facility in the US. Various control technologies have been developed, tested, or used over the past 50 years for control of volatile radionuclide emissions from used fuel reprocessing ...
Nick R. Soelberg, Troy G. Garn, Mitchell R. Greenhalgh, Jack D. Law, Robert Jubin, Denis M. Strachan, Praveen K. Thallapally, Candido Pereira   +7 more
wiley   +1 more source

Decay Heat Removal in GEN IV Gas‐Cooled Fast Reactors

Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009
The safety goal of the current designs of advanced high‐temperature thermal gas‐cooled reactors (HTRs) is that no core meltdown would occur in a depressurization event with a combination of concurrent safety system failures. This study focused on the analysis of passive decay heat removal (DHR) in a GEN IV direct‐cycle gas‐cooled fast reactor (GFR ...
Lap-Yan Cheng, Thomas Y. C. Wei, Colin Mitchell   +2 more
wiley   +1 more source

Gas‐Cooled Fast Reactor: A Historical Overview and Future Outlook

Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009
A review is given of developments in the area of Gas‐Cooled Fast Reactors (GCFR) in the period from roughly 1960 until 1980. During that period, the GCFR concept was expected to increase the breeding gain, the thermal efficiency of a nuclear power plant, and alleviate some of the problems associated with liquid metal coolants.
W. F. G. van Rooijen, Guglielmo Lomonaco
wiley   +1 more source

Operation and Utilisation of the High Flux Reactor - Annual Report 2009 [PDF]

, 2010
The High Flux Reactor (HFR) at Petten is managed by the Institute for Energy (IE) of the EC - DG JRC and operated by NRG who are also licence holder and responsible for commercial activities.
CHARLTON Kevin, D'AGATA Elio, DE GROOT Sander, FUETTERER Michael, HANIA Ralph, HEGEMAN J.b.j.w., KLAASSEN F., LUZGNIVA N., MAGIELSEN A.j., MANTEN JAN, NIEVAART Sander, OHMS Carsten, VAN TIL S., VERVECKEN M., VREELING J. A.   +14 more
core   +1 more source

Measurement of thermal expansion anisotropy in Be12Ti and Be12V [PDF]

, 2023
ORCID　0000-0001-8067-8732Be12Ti and Be12V are promising candidates for neutron multipliers in solid breeding blankets, which is used in a bulk form to achieve the fuel tritium self-sufficiency.
127539, KIM, Jae-Hwan, MUKAI, Keisuke, NAKAMICHI, Masaru   +3 more
core   +1 more source

Thermomechanical characterization of advanced ceramic breeder beds for fusion blankets [PDF]

, 2018
Ein Tritium-Brutblanket (BB) ist ein unverzichtbares Bauteil für den Fusionsdemonstrationsreaktor (DEMO), um die Selbstversorgung des Reaktors mit erbrütetem Tritium sicherzustellen.
Pupeschi, Simone
core   +2 more sources

Status of maturation of critical technologies and systems design: Breeding blanket [PDF]

, 2022
The scope of the EUFOfusion Work Package Breeding Blanket is to develop a blanket concept for the EU DEMO reactor; this includes the blanket segments inside the Vacuum Vessel and the related Tritium Extraction/Removal Systems.
Arbeiter, F., Arena, P., Aubert, J., Boccaccini, L. V., Bühler, L., Cristescu, I., Eboli, M., Forest, L., Harrington, C., Hernandez, F., Knitter, R., Neuberger, H., Nevo, A. Del, Rapisarda, D., Sardain, P., Spagnuolo, G. A., Utili, M., Vala, L., Venturini, A., Vladimirov, P., Zhou, Guangming   +20 more
core   +2 more sources