Thermal Hydraulics Analysis of Pressurized Water Reactor (PWR)

Abstract

Thermal Hydraulics Analysis of PWR The seminar sought a concise analysis of the thermal hydraulics of the Pressurized water reactor (PWR) Nuclear Power plant model in a broad sense, there are two types of two circuit nuclear power plant units, those with water-water reactor of a non-boiling type and those with a gas cooled reactor. The PWR model falls under the category of the former and comprises of a reactor, core, coolant pump, pressurizer, steam generator, turbine, condenser, feed pump and electricity generator. The two circuit plant model with non-boiling reactors has its advantages as well as drawbacks. On the advantage side it has no radioactivity carryover into the steam turbine, possesses good dynamic qualities and has relatively low requirements for chemical water treatment. On its disadvantageous angle it marred by sophistication and increase in plant price, low thermal efficiency and has technological constraints in the production of nuclear steam supply. The thermal hydraulics of a nuclear power reactor involves the analysis of the heat generation process in the reactor core and how the heat generated is utilized to produce steam which drives the turbine. There is so much heat which a coolant can remove before it experiences a thermal crisis which is a sudden and drastic deterioration of its ability to remove heat from the fuel. When a thermal crisis occurs the cladding overheats and fails, thus releasing fission products. Thermal hydraulics has the potential of being relevant to the Nigerian Nuclear Regulatory Authority (NNRA) in fulfilling its role as a regulatory body as regulators in collaboration with advanced laboratories could develop codes to analyse a thermal crises scenario and help regulators to validate the authenticity of result of thermal hydraulics submitted by operators. Furthermore, the regulators could organize examinations and trainings for reactor operating engineers to ascertain the level of their knowledge on the core components of the heat removal system before they can be issued a licence as reactor engineers. Lastly, it is recommended that the authority should carry out training on the usage of thermal hydraulics code for its staff members which put the authority in a better position to conveniently and justly exercise its duties as a regulatory body as well as ensuring compliance with the cardinal points of its establishment. Presented by Odii Christopher Joseph