نتایج جستجو برای: fission reactor core control
تعداد نتایج: 1561679 فیلتر نتایج به سال:
In the first half of the 20 century nuclear fusion and fission were both seen as processes that could potentially be harnessed as a powerful energy source. Research into fusion began in the 1920’s, but it was too technically challenging to make a working fusion reactor. Fission developed much more successfully during the Second World War, when North America’s Manhattan Project attempted to use ...
The bulk irradiation of materials with 10-30 MeV protons promises to advance the study radiation damage for fission and fusion power plants. Intermediate energy proton beams can now be dedicated within university-scale laboratories. This paper describes first such facility, an Ionetix ION-12SC cyclotron producing 12 beams. Samples are mm-scale tensile specimens thicknesses up 300 um, mounted a ...
Geomagnetic field reversals and changes in intensity are understandable from an energy standpoint as natural consequences of intermittent and/or variable nuclear fission chain reactions deep within the Earth. Moreover, deep-Earth production of helium, having (3)He/(4)He ratios within the range observed from deep-mantle sources, is demonstrated to be a consequence of nuclear fission. Numerical s...
Although there have been some severe nuclear accidents such as Three Mile Island (USA), Chernobyl (Ukraine) and Fukushima (Japan), nuclear fission energy is still a source of clean energy that can substitute fossil fuels in a centralized way and in a great amount with commercial availability and economic competitiveness. Since the pressurized water reactor (PWR) is the most widely used nuclear ...
nuclear cross sections that determine core multiplication strongly depend on core temperature (e.g., the doppler, moderator density effects etc). on the other hand, since this heat is generated by the neutron flux in the reactor core, the temperature distribution in the core will depend heavily on its neutronic behavior. fuel centerline temperature could be the limiting constraint on reactor po...
The only significant development of the AUS system has been an extension.of the available cross-sections. That portion of the ENDF/B V data files which is unrestricted has been acquired from the IAEA Nuclear Data Section and the data processed for the AUS.ENDF2006 group library as required. In particular, a large set of fission product data has been processtid, sufficient for calculations of bo...
Silicon carbide (SiC) is a competitive candidate material to be used in several advanced and Generation-IV nuclear reactor designs as neutron moderator, fuel coating, cladding, or core structural material. Many studies have been performed investigate the durability of SiC severe environment reactor. However, nature behavior defect induced by irradiation are still not fully understood. This pape...
in this work, we had examined 7 different types of neutron sources -an isotropic point source, sending 14.1(mev) monoenergetic neutrons ,an spherical source with 30 micron radius sending 14.1 (mev) monoenergetic neutrons, and a 30 micron radius spherical source having gaussian fusion energy spectrum from a d-t fusion, with different bandwidths -1,10,50,100 and 1000 kev and investigated 5 differ...
This paper attempts to summarize the actual problematic of reactor antineutrino energy spectra in the frame of fundamental and applied neutrino physics. Nuclear physics is an important ingredient of reactor antineutrino experiments. These experiments are motivated by neutrino oscillations, i.e. the measure of the 13 mixing angle. In 2011, after a new computation of the reactor antineutrino ener...
Multi-pass refueling scheme is a highlighted feature of pebble bed HTGR which spatially mixes the burnup calculation inside core. Such relate in one region core to others and thus affects uncertainty propagation nuclear data, e.g. fission product yield. In this work, thermal neutron induced U-235 yield uncertainties are propagated HTR-PM models with various schemes V.S.O.P. code. And effect mul...
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