Thermal Hydraulics in Reactor Vessel of Fast Breeder 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...

Reactor Pressure Vessel Embrittlement—i

Optimal Reactor Length of an Auto-Thermal Ammonia Synthesis Reactor

This paper presents the simulation of auto-thermal ammonia synthesis reactor. Our target here is to estimate the optimal reactor length which will give the maximum profit from the ammonia reactor. There are many literatures which are interested in ammonia simulation in the past but all need some corrections due to either uncorrected model used or uncorrected algorithm. We used here the ODE45 so...

Experimental Approach to Flow Field Evaluation in Upper Plenum of Reactor Vessel for Innovative Sodium Cooled Fast Reactor

In Japan Atomic Energy Agency, an innovative sodium cooled fast reactor of 1500MWe class, JSFR, has been investigated on the Fast Reactor Cycle Technology Development project. A compact reactor vessel (R/V) and a column type upper inner structure with a radial slit for an arm of a fuel-handling machine are adopted. These result in increase of the spatial-averaged velocity on the horizontal cros...

Advanced Fast Reactor:

The AFR concept is being developed at Argonne National Laboratory, as an extension of earlier work done on the Integral Fast Reactor (IFR). That work was undertaken specifically to resolve some pressing technical issues in safety, waste management, nonproliferation, and economics. Also important, however, was the fundamental fact that the efficient utilization of uranium resources is crucial to...