Results 221 to 230 of about 28,400 (253)

Overview of fuel retention in composite and tungsten limiters

Journal of Nuclear Materials, 2002
A number of materials, in a form of limiters, have been tested at the TEXTOR tokamak as candidates for plasma facing components in future devices. The results for fuel distribution and content in sole tungsten and composites (vacuum plasma sprayed tungsten layer on graphite and a B4C coating on copper) are reported and compared with earlier obtained ...
Rubel, M., Philipps, V., Pospieszczyk, A., Tanabe, T., Kötterl, S.   +4 more
openaire   +2 more sources

Theories of Swelling and Gas Retention in Ceramic Fuels

Nuclear Applications and Technology, 1970
AbstractThe development of models of fuel-element performance requires, among other things, a detailed, quantitative understanding of fuel swelling and fission gas release.
openaire   +1 more source

Particle Balance and Fuel Retention in Tore Supra

Fusion Science and Technology, 2009
Fuel retention in carbon plasma-facing components (PFCs) is such a major concern for next-step operation that it could prevent the use of this material in the D-T phase of ITER.
openaire   +1 more source

Volatile species retention during metallic fuel casting

Journal of Nuclear Materials, 2013
Abstract Metallic nuclear fuels are candidate transmutation fuel forms for advanced fuel cycles. Through the operation of the Experimental Breeder Reactor II metallic nuclear fuels have been shown to be robust and easily manufactured. However, concerns have been raised concerning loss of americium during the casting process because of its high vapor ...
Randall S. Fielding, Douglas L. Porter
openaire   +1 more source

An overview of fuel retention and morphology in a castellated tungsten limiter

Fusion Engineering and Design, 2008
A castellated tungsten test limiter composed of detachable segments was exposed to plasma discharges in the TEXTOR to kamak operated with graphite main limiters.
M.J. Rubel, G. Sergienko, A. Kreter, A. Pospieszczyk, M. Psoda, E. Wessel   +5 more
openaire   +1 more source

Construction of a fuel retention model for full carbon devices

Physica Scripta, 2011
Hydrogen and deuterium retention in the plasma-facing carbon tiles used as divertor plates, baffle plates (BPs) and first wall (FW) tiles of JT-60U, which is a full carbon device and operated at 573 K, was measured by means of thermal desorption spectroscopy and a model was constructed for fuel retention including the whole area of JT-60U.
M Yoshida, T Tanabe, T Hayashi, H Nakano, K Masaki, K Itami   +5 more
openaire   +1 more source

Analysis of fuel retention on MAST by global gas balance

Plasma Physics and Controlled Fusion, 2010
The retention of deuterium fuel during MAST discharges has been studied using the method of global gas balance. The results show that with inter-shot 4He-GDC, the total number of particles retained for a discharge increases with the total number of injected particles, and the total retention fraction stays very high, and can be almost 100%. However, it
J Huang, S Lisgo, G Maddison
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Fuel retention and recovery in natural and MGI disruptions on KSTAR

Journal of Nuclear Materials, 2013
Abstract Fuel retention and recovery are studied during natural and Massive Gas Injection (MGI) induced disruptions in KSTAR with full graphite wall. The amount of released particles in natural disruptions in 15 s after the discharge is ∼5–10 times higher than that of non-disruption shots, but the difference is only ∼  2 MGI induced disruptions ...
Y.W. Yu, S.H. Hong, S.W. Yoon, K.P. Kim, W.C. Kim, D.C. Seo   +5 more
openaire   +1 more source

Post-mortem measurements of fuel retention at JET with MKII-SRP divertor

Journal of Nuclear Materials, 2009
The deuterium inventory at JET after 2001–2004 operational campaign has been determined using nuclear reaction analysis (NRA) and secondary ion mass spectrometry (SIMS). A full poloidal set of divertor tiles and a set of outer poloidal limiter (OPL) tiles were analysed providing an estimation for the total deuterium retention of about 66 g.
Coad, J. P., Hole, D. E., Koivuranta, Seppo, Renvall, T., Rubel, M., Vainonen-Ahlgren, E., Widdowson, A., JET-EFDA Contributors,, Likonen, Jari   +8 more
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Post-mortem measurements of fuel retention at JET in 2007–2009 experimental campaign

Journal of Nuclear Materials, 2013
The deuterium inventory at Joint European Torus (JET) after the 2007–2009 experimental campaign has been evaluated using Nuclear Reaction Analysis (NRA) and Secondary Ion Mass Spectrometry (SIMS). A full poloidal set of divertor tiles were analysed providing estimation for the total deuterium retention of about 48 g.
Likonen, Jari, Hakola, Antti, Coad, Paul, Widdowson, A., Hole, D.E., Rubel, M., JET-EFDA contributors, Koivuranta, Seppo   +7 more
openaire   +3 more sources