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International Journal of Earth & Environmental Sciences Volume 4 (2019), Article ID 4:IJEES-166, 9 pages
https://doi.org/10.15344/2456-351X/2019/166
Review Article
Heat Pipe Application In Fission Driven Nuclear Power Plant

Bahman Zohuri

Department of Electrical Engineering and Computer Science, University of New Mexico, Albuquerque, New Mexico 87131, USA
Consultant at Galaxy Advanced Engineering, Albuquerque, New Mexico 87111, USA
Dr. Bahman Zohuri, Department of Electrical Engineering and Computer Science, University of New Mexico, Albuquerque, New Mexico 87131, USA; E-mail: zohurib@unm.edu
26 April 2019; 24 June 2019; 26 June 2019
Zohuri B (2019) Heat Pipe Application In Fission Driven Nuclear Power Plant. Int J Earth Environ Sci 4: 166. doi: https://doi.org/10.15344/2456-351X/2019/166

Abstract

As the global population grow, so will the demand for energy to ensure standards of living, health and life expectancy, literacy and opportunity, etc. To cope with this energy demand, nuclear energy, which is believed to be sustainable, clean and safe, has been extensively advocated. To enhance the future role of nuclear energy systems, a generation of innovative nuclear energy systems, known as Generation IV, has been proposed to replace the current Gen II/III reactors and Gen III+ reactors that will be deployed in near future.

A new concept involving the use of heat pipes as control devices for nuclear reactors will be investigated in this book. The feature of the concept is that the heat pipe will contain a fissionable material as the working fluid. The primary purpose of the heat pipe will be to change the amount of fuel within a reactor Instead of the usual purpose of transferring heat.

In conjunction with Heat Pipe (HP) in this book we have also allocated a section on Directed Reactor Auxiliary Cooling System (DRACS) and presenting the scalar analysis for it as well in particular in respect to Advanced High Temperature Reactors (AHTRs) and Small Modular Reactor (SMR) of Generation IV (GEN-IV) such as Molten Salt Reactor is shape of the Pebble-Bed Reactor (PBR). The Pebble-Bed Reactor (PBR) is a design for a graphite-moderated, gas-cooled nuclear reactor. It is a type of very-high-temperature reactor (VHTR), one of the six classes of nuclear reactors in the Generation IV initiative.