Relative to coal fired and natural gas fired power plants, nuclear power plants are more expensive to build but less expensive to run. This annex describes advanced construction methods to reduce nuclear power's construction costs, mainly by shortening the time needed to build a plant. Each of the methods described below has been used in one or more of the projects listed in Table IV-1. None is...

The effect of variation in thermal conductivity of light water reactor fuel elements on core response during loss-of-coolant accident scenarios is examined. Initially, a simplified numerical analysis is utilized to determine the time scales associated with dissipation of stored energy from the fuel into the coolant once the fission reaction is stopped. The analysis is then followed by full reac...

In order to optimize and validate the design and the operation of its nuclear power plants facilities, EDF (Electricité de France) uses a proprietary tool called LEDA to perform static and dynamic simulation at the system level. EDF wishes to replace LEDA by state-of-the-art off-the-shelf tools, mainly to reduce maintenance cost while keeping up with the latest trend in modeling and simulation ...

The hydrothermal synthesis of zeolites carried out in batch reactors takes a time so long (typically, on the order of days) that the crystallization of zeolites has long been believed to be very slow in nature. We herein present a synthetic process for ZSM-5, an industrially important zeolite, on the order of seconds in a continuous flow reactor using pressurized hot water as a heating medium. ...

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...

An accurate description of the fluid flow and heat transfer within a Pressurized Water Reactor (PWR), for the safety analysis and reactor performance is always desirable. In this paper a mathematical model of the fundamental physical phenomena which are associated to a typical PWR is presented. The mathematical model governs the fluid dynamics in the reactor. Using commercial software CFX, a co...

The modified out-in fuel management strategy was applied to the core loading design for the first four cycles of the Bushehr (Iran-1) KWU designed Pressurized Water Reactor (PWR). The minimum peak-to-average power density was chosen as the objective function of the optimization process. Lattice homogenization and group constants generation were performed by using the LEOPARD computer code. For ...