Test problem for thermal-hydraulics and neutronic coupled calculation fore ALFREAD reactor core

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...

Validation of Reactor Physics-thermal Hydraulics Coupled Calculation in Water-cooled Research Reactors with Laminar Flow Regimes

A collaboration between the University of Florida and the Swiss Federal Institute of Technology, Lausanne (EPFL) has been formed to develop and validate detailed coupled multiphysics models of the zero-power (100 W) CROCUS reactor at EPFL and the 100 kW University of Florida Training Reactor, for the comprehensive analysis of the reactor behavior under transient (neutronic or thermal-hydraulic ...

Monte Carlo Neutronic Analysis of A Loosely Coupled Reactor*

Thermal Hydraulics Design Limits

The following discussion of PWR steady state and transient design limits is extracted from the theses of Carter Shuffler and Jarrod Trant while the BWR discussion is extracted from Paolo Ferroni's thesis (covers steady state only). These limits are a simplified and narrower discussion than the relevant NRC standard review plan you will also be referred to. All materials are directly extracted f...

Optimization of A Thermal Coupled Flow Problem of Semiconductor Melts

In this paper we describe the formal Lagrange-technique to optimize the production process of solid state crystals from a mixture crystal melt. After the construction of the adjoint equation system of the Boussinesq equation of the crystal melt the forward and backward problems (KKT-system) are discretized by a conservative finite volume method.