نتایج جستجو برای: reactor core
تعداد نتایج: 242961 فیلتر نتایج به سال:
In this work, the Isfahan Miniature Neutron Source Reactor (MNSR) is first simulated using the WIMSD code, and its fuel burn-up after 7 years of operation ( when the reactor was revived by adding a 1.5 mm thick beryllium shim plate to the top of its core) and also after 14 years of operation (total operation time of the reactor) is calculated. The reactor is then simulated using the MCNP code,...
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...
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...
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 ...
Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the distribution of heat sources, which is needed to perform the thermal-hydraulic analysis. In this study single heated channel model as a very f...
Tehran Research Reactor (TRR) is in a residential area. Some other characteristics such as aged, relatively full time operation and also being the only available reactor for producing some radioisotopes, are the reasons for special attention to this reactor safety. Recently, a Second Shutdown System (SSS) has been designed for this reactor, which is completely independent and diverse from First...
In order to increase productivity, reduce depreciation, and avoid possible accidents in a system such as fuel rods' melting and overpressure, control of temperature changes in the reactor core is an important factor. There are several methods for solving and analysing the stability of point kinetics equations. In most previous analyses, the effects of various factors on the temperature of the r...
چکیده ندارد.
The 250 kW TRIGA Mark II research reactor, Vienna, operates since 7 March 1962. The initial criticality was achieved with the first core loading of 57 fuel elements (FE) of same type (Aluminium clad fuel with 20% enrichment). Later on due to fuel consumption SST clad 20% enriched FE (s) have been added to compensate the reactor core burn-up. In 1975 high enriched (HEU) TRIGA fuel (FLIP fuel = F...
The neutron eccmomy of a fast reactor is not so significantly affected by neutron capture in the structural materials in the core as is that of a thermal reactor. First, most neutron-capture cross sections increase with de creasing neutron energy, and the neutron population of the liquid-metal fast breeder reactor (Lhl FI~R) contains a far lower percentage of thermal neutrons than does that (I...
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