نتایج جستجو برای: fission reactor core control
تعداد نتایج: 1561679 فیلتر نتایج به سال:
An enhanced comprehension of the fission process is essential to our understanding nuclear dynamics as well other phenomena such stellar nucleosynthesis and reactor spectra that probe fundamental physics. In this paper authors take an important step toward role angular momentum in fission.
The estimation of the neutron fluence at Reactor Pressure Vessel (RPV) is classically carried out by a two-step approach. first step to estimate full core source term whether second calculation consists in transport neutrons from (source term) RPV using fission distribution determined previous step. For this purpose, be accurately fuel pin level for assemblies on border core. To achieve goal, t...
Fission fragments play a pivotal role in understanding the entire nuclear fission process, and their effects are widespread to all applications involving nuclear fission: reactor design and maintenance, waste removal, active and passive integration of nuclear materials, simulations, and the fundamental theories of fission. Currently, experimental data on the characteristic properties of fission...
The contribution describes the new measuring and protection system of the VR-1 training reactor. The measuring and protection system upgrade is an integral part of the reactor I&C upgrade. The new measuring and protection system of the VR-1 reactor consists of the operational power measuring and the independent power protection systems. Both systems measure the reactor power and power rate, ini...
The heat transfer process from pellet to coolant is one of the important issues in nuclear reactor. In this regard, the fuel to clad gap and its physical and chemical properties are effective factors on heat transfer in nuclear fuel rod discussion. So, the energy distribution function of electrons with an energy about 0.5 MeV in fuel rod gap in Busherhr’s VVER-1000 nuclear reactor was investiga...
For either nuclear fusion or generation IV fission reactors to be viable as a commercial energy source the decommissioning and waste disposal solutions must considered during design. A multi-step simulation process combining Monte Carlo Neutron Transport simulations with inventory have been performed estimate activation of steels in key reactor components European Sodium-cooled fast Reactor (ES...
Nuclear reactor modeling has been shifting, over the last decades, towards full-core multiphysics analysis due to ever-increasing safety requirements and complexity of designs innovative systems. This is particularly true for liquid-fuel concepts such as Molten Salt Fast Reactor (MSFR), given their strong intrinsic coupling between thermal-hydraulics, neutronics fuel chemistry. In MSFR, fission...
Recent advances in supercomputers and parallel solver techniques have enabled users to run large simulations problems using millions of processors. Techniques for multiphysics nuclear reactor core simulations are under active development in several countries. Most of these techniques require large unstructured meshes that can be hard to generate in a standalone desktop computers because of high...
Abstract Previous works have demonstrated that the Fourier fundamental mode coefficient (FFMC) is a potential fission source convergence indicator for Monte Carlo k -eigenvalue calculations. Unlike conventional Shannon entropy indicator, it requires no spatial meshing, and its computation computationally inexpensive. However, we found FFMC less sensitive to involving near symmetrical distributi...
reactor core for nuclear power plant (1293 mwe) is of pressurized water reactor (pwr) type , with net electric output of 1200 mwe. the reactor is designed by a german company kwu (krafts werk :union:). in order to introduce the methods of calculation of the reactor core parameters to the students at the institute of nuclear science and technology, and in addition to provide them with the basic ...
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