Core Flow Distribution from Coupled Supercritical Water Reactor Analysis

Numerical Investigation of the Flow and Heat Transfer within the Core Cooling Channel of a Supercritical Water Reactor

Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model

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...

Core Loading Design for Bushehr Pressurized Water Reactor

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 ...

Cross-spectral density measurements in a coupled-core reactor

Cross-spectral density measurements in a coupled-core reactor " (1966). Retrospective Theses and Dissertations. Paper 5371. 1966 Signature was redacted for privacy.

Supercritical Water Radiolysis Chemistry Supercritical Water Corrosion

The direct measurement of the chemistry in reactor cores is extremely difficult. The extreme conditions of high temperature, pressure, and radiation fields, are not compatible with normal chemical instrumentation. There are also problems of access to fuel channels in the reactor core. For these reasons, all reaction vendors and many operators have extensively used theoretical calculations and c...