GRAPHITE MATERIAL IN NUCLEAR REACTOR



Critical Review of the Current State Of Art Knowledge about the Use of Graphite Material in Nuclear Reactor

Abstract

This research study reconsiders the current state of the art on the use of graphite material in nuclear reactor and summarizes the necessary safety precautions to deal with this material, a presentation of work and future study. Because of this study was undertaken to validate the numbers of such computer WIMS-D / 4 and service to investigate the criticality of natural uranium fueled, light water cooled, heavy water moderated reactors and graphite echoed such Nacional Experimental Reactor (NRX) and Canadian Indian Reactor (CIR). These figures are then used to seek an expansion of the reactor core resistant. It was discovered that the replacement of the cooling light water with heavy water moderation and expanded, the center can be an employee of a degree of power less than half in contrast to the musical power of NRX / CIR, but the flow of neutrons will remain unchanged. This center will be smaller in size and therefore will be savings in necessary quantities of D2O, graphite and fuel. This causes much less plutonium more engrossment of 240Pu, if the burn is more than 2800 MWD / T. Moreover, it was discovered that the nullity of the coefficient of refrigerant will be less favorable and thus the system will be safer in contrast to initial NRX / CIR design.

A procedure for easy combustion oxidant, using a sample oxidizer financial reporting have been individually to work out the 14C and 3H in graphite and business case. Through this procedure, the time field experiment can be reduced to 2-3 min. The detection limits for 3 hours and 14C are 0.96 and 0.58 Bq / g of graphite and 0.11 and 0.06 Bq / g solid, respectively. Cross contamination of 14C and tritium in the bases of the tests is less than 0.2%. The interference of other radionuclides in the celebration of 14C and tritium in graphite is insignificant. The accuracy of analysis, said the process for additional reference, is better than 95%. In addition, an unpleasant process of digestion, in addition, has been used to analyze the graphite and healthy companies, to allow evaluation of the process has evolved here. The two procedures show good statement for the samples of graphite. Graphite tests were assembled from the Danish Reactor DR-2 and DR-3, in addition to two centers of drilled solids in the Danish reactor DR-2, they were analyzed for 3 hours and 14C, using the procedure that has been developed.

Critical Review of the Current State Of Art Knowledge about the Use of Graphite Material in Nuclear Reactor

1. Introduction

This research study focuses on dismantling of nuclear facilities, radioactivity desires of various components to be evaluated. In the center of the reactor, the radioactivity in the reactor reaches the main graphite and construction materials. Due to large volumes, and solid graphite subsidies are substantial low-medium radioactive ...