http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
The CONTIN algorithm and its application to determine the size distribution of microgel suspensions
Scotti, A.,Liu, W.,Hyatt, J. S.,Herman, E. S.,Choi, H. S.,Kim, J. W.,Lyon, L. A.,Gasser, U.,Fernandez-Nieves, A. American Institute of Physics 2015 The Journal of chemical physics Vol.142 No.23
<P>We review a powerful regularization method, known as CONTIN, for obtaining the size distribution of colloidal suspensions from dynamic light scattering data. We show that together with the so-called L-curve criterion for selecting the optimal regularization parameter, the method correctly describes the average size and size distribution of microgel suspensions independently characterized using small-angle neutron scattering. In contrast, we find that when using the default regularization process, where the regularizer is selected via the 'probability to reject' method, the results are not as satisfactory.</P>
Characterisation and Durability of a Vitrified Wasteform for Simulated Chrompik III Waste
Walling, Sam A.,Gardner, Laura J.,Pang, H.K. Celine,Mann, Colleen,Corkhill, Claire L.,Mikusova, Alexandra,Lichvar, Peter,Hyatt, Neil C. Korean Radioactive Waste Society 2021 방사성폐기물학회지 Vol.19 No.3
Legacy waste from the decommissioned A-1 nuclear power plant in the Slovak Republic is scheduled for immobilisation within a tailored alkali borosilicate glass formulation, as part of ongoing site cleanup. The aqueous durability and characterisation of a simulant glass wasteform for Chrompik III legacy waste, was investigated, including dissolution experiments up to 112 days (90℃, ASTM Type 1 water). The wasteform was an amorphous, light green glassy product, with no observed phase separation or crystalline inclusions. Aqueous leach testing revealed a suitably durable product over the timescale investigated, comparing positively to other simulant nuclear waste glasses and vitreous products tested under similar conditions. Iron and titanium rich precipitates were observed to form at the surface of monolithic samples during leaching, with the formation of an alkali deficient alteration layer behind these at later ages. Overall this glass appears to perform well, and in line with expectations for this chemistry, although longer-term testing would be required to predict overall durability. This work will contribute to developing confidence in the disposability of vitrified Chrompik legacy wastes.
Control of plasma profiles in DIII-D discharges
Gohil, P,Evans, T E,Ferron, J R,Moyer, R A,Petty, C C,Burrell, K H,Casper, T A,Garofalo, A M,Hyatt, A W,Jayakumar, R J,Kessel, C,Kim, J Y,La Haye, R J,Lohr, J,Luce, T C,Makowski, M A,Mazon, D,Menard, Published jointly by The Institute of Physics and 2006 Plasma physics and controlled fusion Vol.48 No.a5
<P>Active control of plasma profiles is an essential requirement for operating within plasma stability limits, for steady-state operation and for optimization of the plasma performance. In DIII-D, plasma profiles have been actively controlled using various actuators in the following manner: (a) real time closed loop control of the <I>q</I> profile evolution using electron cyclotron heating and neutral beam injection as actuators; (b) active control of the density and pressure profiles in quiescent H-mode and quiescent double barrier plasmas using electron cyclotron current drive (ECCD) and pellet injection; (c) active control of the edge profiles to suppress edge localized modes using resonant magnetic perturbation with toroidal mode number <I>n</I> = 3, (d) real time control of the current density profile to suppress neoclassical tearing modes using localized deposition of co-ECCD.</P>