نتایج جستجو برای: fission reactor coolant

تعداد نتایج: 45549  

2001
V. Tang R. Parker

In this preliminary scoping study, post-accident temperature transients of several fusion-fission designs utilizing ITER-FEAT-like parameters and fission pebble bed fuel technology are examined using a 1-D cylindrical Matlab heat transfer code along with conventional fission decay heat approximations. Scenarios studied include systems with no additional passive safety features to systems with m...

2008
Y. Chen J. Zhang H. Chen J. Li

In advanced nuclear energy systems, lead-alloys (e.g., lead, leadbismuth eutectic) emerge as strong candidates for transmutation and advanced reactor systems as nuclear coolants and high-power spallation neutron targets. However, it is widely recognized that corrosion of materials caused by lead-alloys presents a critical barrier to their industrial use. A few experimental research and developm...

Journal: :Journal of Nuclear Medicine 2016

2014
K. Anandhakumar P. Ponmurugan

In this paper, Particle Filter algorithm has been employed for estimating the states namely concentration and temperature of a Continuous Stirred Tank Reactor (CSTR) and simulation results are presented. The propagation of particles through the nonlinear system model for the state estimation has been discussed. The states of the system are estimated by using the Particle Filter algorithm under ...

Journal: :Journal of Nuclear Science and Technology 2011

2003
H. Y. Khater

LIBRA-SP is a 1000 MWe light ion beam power reactor design study. The reactor structure is made of a low activation ferritic steel and uses LiPb as a breeder. The total activities in the blanket and reflector at shutdown are 721 MCi and 924 MCi, respectively. Hands-on maintenance is impossible anywhere inside the reactor chamber. The biological dose rates near the diode are too high at all time...

2008
J. Jordanova

The work presents the results of the detailed analyses performed on the shielding capability of HCLL DEMO-type fusion reactor. The analysis is based on three-dimensional calculations with the Monte Carlo code MCNP-4C and consists in assessment of radiation loads to the super-conducting TF-coil at the inboard side of the reactor. A suitable 20-sector model of DEMO reactor, based on the reactor p...

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