scholarly journals The NEREUS Installation — The Non-Nuclear Part (GT)

Author(s):  
G. A. K. Crommelin

This paper should be read in conjunction with the paper The NEREUS installation — the nuclear part (HTR). This part will discuss the non-nuclear part of the nuclear gas turbine installation called the NEREUS installation. It will discuss the non-nuclear part of a modular energy production installation consisting of an inherently safe, helium cooled, graphite moderated nuclear reactor, which acts as heat source to an energy conversion unit consisting of a closed-cycle recuperative gas turbine driving a generator (abbreviated as HTR-GT) (see also ref. 11 and 12). The paper is based upon an ongoing study, supported by specialists and scientists, among others of the Delft University of Technology, of most aspects concerning this type of power producing unit. This paper will discuss its (non-nuclear) components, efficiency, market potential and costing in comparison with existing and comparable installations. So it will report on a pre-feasibility study, based upon existing reports, publications, estimations by specialists and from active projects.

Author(s):  
S. T. Robinson

During the past few months there has been a renewed expression of interest in the high-temperature gas-cycle reactor coupled with a closed-cycle gas turbine in a single loop as a means of utilizing the energy available from nuclear fission. At present the procurement of two closed-cycle gas-turbine plants is planned in this country, both of which are suitable for use with a gas-cycle nuclear reactor as a heat source. These plants differ widely in output, purpose and the nature of the working fluid. One of the questions repeatedly raised during their design was the effect of the nature and characteristics of the working fluid on the design of the nonnuclear components. This pointed to the desirability of a specific study along these lines, which study was conducted by the author’s firm and is partially reported herein.


Atomic Energy ◽  
2005 ◽  
Vol 98 (1) ◽  
pp. 21-31 ◽  
Author(s):  
A. V. Vasyaev ◽  
V. F. Golovko ◽  
I. V. Dmitrieva ◽  
N. G. Kodochigov ◽  
N. G. Kuzavkov ◽  
...  

Author(s):  
Ali Afrazeh ◽  
Hiwa Khaledi ◽  
Mohammad Bagher Ghofrani

A gas turbine in combination with a nuclear heat source has been subject of study for some years. This paper describes the advantages of a gas turbine combined with an inherently safe and well-proven nuclear heat source. The design of the power conversion system is based on a regenerative, non-intercooled, closed, direct Brayton cycle with high temperature gas-cooled reactor (HTGR), as heat source and helium gas as the working fluid. The plant produces electricity and hot water for district heating (DH). Variation of specific heat, enthalpy and entropy of working fluid with pressure and temperature are included in this model. Advanced blade cooling technology is used in order to allow for a high turbine inlet temperature. The paper starts with an overview of the main characteristics of the nuclear heat source, Then presents a study to determine the specifications of a closed-cycle gas turbine for the HTGR installation. Attention is given to the way such a closed-cycle gas turbine can be modeled. Subsequently the sensitivity of the efficiency to several design choices is investigated. This model is developed in Fortran.


Author(s):  
Colin F. McDonald

This paper has been written exactly 50 years after the first disclosure of a closed-cycle gas turbine concept with a simplistic uranium heater. Clearly, this plant was ahead of its time in terms of technology readiness, and the closed-cycle gas turbine was initially deployed in a cogeneration mode burning dirty fuels (e.g., coal, furnace gases). In the 1950s through the mid 1980s about 20 of these plants operated providing electrical power and district heating for European cities. The basic concept of a nuclear gas turbine plant was demonstrated in the USA on a small scale in 1961 with a mobile closed-cycle nitrogen gas turbine [330 KW(e)] coupled with a nuclear reactor. In the last three decades, closed-cycle gas turbine research and development, particularly in the U.S. has focused on space power systems, but today the utility size gas turbine-modular helium reactor (GT-MHR) is on the verge of being realized. The theme of this paper traces the half century of closed-cycle gas turbine evolution, and discusses the recent enabling technologies (e.g., magnetic bearings, compact recuperator) that now make the GT-MHR close to realization. The author would like to dedicate this paper to the late Professor Curt Keller who in 1935 filed the first closed-cycle gas turbine patent in Switzerland, and who exactly 50 years ago, first described a power plant involving the coupling of a helium gas turbine with a uranium heater.


Author(s):  
K. N. Pradeep Kumar ◽  
A. Tourlidakis ◽  
P. Pilidis

The Starting up and Shutting down of a closed cycle gas turbine power plant needs special attention due to the inter-dependable nature of the components. Achieving self-sustainability in a fast and efficient way within the mechanical constraints is the challenge in the start-up of a closed cycle. The Nuclear reactor as the heat source will add more complexity to the system. The paper looks into the various options available for the start up and shutdown of a closed cycle Helium turbine using a gas cooled reactor as the heat source. A comparative analysis of these options is carried out by simulating various operating scenarios using a Transient Simulation Computer Programme especially prepared for an HTGR Project called PBMR (Pebble Bed Modular Reactor), which is being carried out in South Africa. The simulation was focused on the power conversion side of the plant, which includes all the Turbocompressors, Turbogenerator, Heat exchangers, Valves etc. Based on the analysis and its findings, an outline of a start up and shutdown procedure for a 3-shaft Closed Cycle Turbine Power Plant using hot gas injection is proposed in the paper.


Author(s):  
Colin F. McDonald

With the capability of burning a variety of fossil fuels, giving high thermal efficiency, and operating with low emissions, the gas turbine is becoming a major prime-mover for a wide spectrum of applications. Almost three decades ago two experimental projects were undertaken in which gas turbines were actually operated with heat from nuclear reactors. In retrospect, these systems were ahead of their time in terms of technology readiness, and prospects of the practical coupling of a gas turbine with a nuclear heat source towards the realization of a high efficiency, pollutant free, dry-cooled power plant has remained a long-term goal, which has been periodically studied in the last twenty years. Technology advancements in both high temperature gas-cooled reactors, and gas turbines now make the concept of a nuclear gas turbine plant realizable. Two possible plant concepts are highlighted in this paper, (1) a direct cycle system involving the integration of a closed-cycle helium gas turbine with a modular high temperature gas cooled reactor (MHTGR), and (2) the utilization of a conventional and proven combined cycle gas turbine, again with the MHTGR, but now involving the use of secondary (helium) and tertiary (air) loops. The open cycle system is more equipment intensive and places demanding requirements on the very high temperature heat exchangers, but has the merit of being able to utilize a conventional combined cycle turbo-generator set. In this paper both power plant concepts are put into perspective in terms of categorizing the most suitable applications, highlighting their major features and characteristics, and identifying the technology requirements. The author would like to dedicate this paper to the late Professor Karl Bammert who actively supported deployment of the closed-cycle gas turbine for several decades with a variety of heat sources including fossil, solar, and nuclear systems.


2020 ◽  
Vol 6 (2) ◽  
Author(s):  
Emmanuel O. Osigwe ◽  
Arnold Gad-Briggs ◽  
Theoklis Nikolaidis ◽  
Pericles Pilidis ◽  
Suresh Sampath

Abstract As demands for clean and sustainable energy renew interests in nuclear power to meet future energy demands, generation IV nuclear reactors are seen as having the potential to provide the improvements required for nuclear power generation. However, for their benefits to be fully realized, it is important to explore the performance of the reactors when coupled to different configurations of closed-cycle gas turbine power conversion systems. The configurations provide variation in performance due to different working fluids over a range of operating pressures and temperatures. The objective of this paper is to undertake analyses at the design and off-design conditions in combination with a recuperated closed-cycle gas turbine and comparing the influence of carbon dioxide and nitrogen as the working fluid in the cycle. The analysis is demonstrated using an in-house tool, which was developed by the authors. The results show that the choice of working fluid controls the range of cycle operating pressures, temperatures, and overall performance of the power plant due to the thermodynamic and heat properties of the fluids. The performance results favored the nitrogen working fluid over CO2 due to the behavior CO2 below its critical conditions. The analyses intend to aid the development of cycles for generation IV nuclear power plants (NPPs) specifically gas-cooled fast reactors (GFRs) and very high-temperature reactors (VHTRs).


Author(s):  
Gulian A. K. Crommelin ◽  
Walter F. Crommelin

This study is about a much discussed and recommended application of a nuclear gas turbine and was undertaken at the request of many visitors to the Nuclear Gas Turbine stand at the ASME IGTI 2002 in Amsterdam. Apparently, the specifications of the NEREUS plant led their thoughts to small-scale energy production combined with fresh water production. This thought fits well into the basic idea that: Energy equals Electricity, Heat and Fresh Water. The NEREUS project is a non-profit organisation seeking to expand the use of Small Scale Nuclear Power Generation. This paper discusses the possibilities to produce fresh water with a NEREUS inherently safe nuclear power plant. The acronym NEREUS describes very well the goals of this project and stands for: A Natural safe, Efficient, Reactor, Easy to operate, Ultimately simple and Small. Fresh water can be produced using any fossil fuelled energy conversion unit, but this study works out how the advantages of a gas turbine in combination with an inherently safe and well-proven nuclear heat source combines the advantages of a gas turbine with the logistic advantages of nuclear power. The paper starts with an introduction on why the energy conversion branch should pay more attention to fresh water production. Secondly the paper gives an overview of the main characteristics of the nuclear heat source. Thirdly the paper briefly explains the most common methods used for fresh water produced. Finally the paper will discuss the conclusion of this study, which was: The ENERGY demand of 27648 people can be fully and affordably satisfied in both quantity and quality, with a well-proven, inherently safe, self controlling nuclear pebble-bed 20 MWth reactor. Such a reactor is suitable for unmanned operation with a three year refuelling and maintenance cycle, and with the dimensions of 10 × 10 × 10 meters.


Author(s):  
Emmanuel O. Osigwe ◽  
Arnold Gad-Briggs ◽  
Theoklis Nikolaidis ◽  
Pericles Pilidis ◽  
Suresh Sampath

With renewed interest in nuclear power to meet the world’s future energy demand, the Generation IV nuclear reactors are the next step in the deployment of nuclear power generation. However, for the potentials of these nuclear reactor designs to be fully realized, its suitability, when coupled with different configurations of closed-cycle gas turbine power conversion systems, have to be explored and performance compared for various possible working fluids over a range of operating pressures and temperatures. The purpose of this paper is to carry out performance analysis at the design and off-design conditions for a Generation IV nuclear-powered reactor in combination with a recuperated closed-cycle gas turbine and comparing the influence of carbon dioxide and nitrogen as working fluid in the cycle. This analysis is demonstrated in GTACYSS; a performance and preliminary design code developed by the authors for closed-cycle gas turbine simulations. The results obtained shows that the choice of working fluid controls the range of cycle operating pressures, temperatures and overall performance of the power plant due to the thermodynamic and heat properties of the fluids. The performance results favored the nitrogen working fluid over CO2 due to the behavior CO2 below its critical conditions.


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