scholarly journals OVERNIGHT COST ESTIMATION OFINDONESIA’S COGENERATION POWER PLANT FOR INDUSTRIAL PROCESSES

2019 ◽  
Vol 20 (2) ◽  
pp. 95
Author(s):  
Rizki Firmansyah Setya Budi ◽  
Arum Puni Rijanti ◽  
Sahala M. Lumbanraja ◽  
Elok S. Amitayani ◽  
Moch. Djoko Birmano ◽  
...  
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Economic Analysis ◽  
Cost Estimation ◽  
Scaling Law ◽  
Industrial Processes ◽  
Estimation Result ◽  
Cost Scaling ◽  
High Temperature Gas

Indonesia’s cogeneration power plant for industrial processes (PeLUIt) is needed to be implemented in Indonesia. Economic analysis is an important factor for PeLUIt implementation. One of the data that needs in the analysis is overnight cost. This research estimates HTGR’s overnight cost by using scaling law.By using the estimated value, it can be calculated the PeLUIt overnight cost. The research’s purpose is to obtain an estimation of overnight costs of PeLUIt. The estimation result shows the overnight cost of PeLUIt. PeLUIt 10 MWth has an overnight cost 166,26 million USD. PeLUIt 30 MWth has an overnight cost 233,49 million USD. PeLUIt 50 MWth has an overnight cost 281,31 million USD. PeLUIt 100 MWth has an overnight cost 371,86 million USD. PeLUIt 350 MWth has an overnight cost 657,16 million USD.Keywords: PeLUIt; Estimation; High temperature gas-cooled reactor; Overnight cost; Scaling law

Verification of Alarm Displays for the Nuclear Power Plant With Two Modular High-Temperature Gas-Cooled Reactors

2018 ◽  
Author(s):  
Jia Qianqian ◽  
Guo Chao ◽  
Li Jianghai ◽  
Qu Ronghong
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Modular Design ◽  
Early Stage ◽  
Integrated System ◽  
Alarm System ◽  
Control Room ◽  
High Temperature Gas

The nuclear power plant with two modular high-temperature gas-cooled reactors (HTR-PM) is under construction now. The control room of HTR-PM is designed. This paper introduces the alarm displays in the control room, and describes some verification and validation (V&V) activities of the alarm system, especially verification for some new human factor issues of the alarm system in the two modular design. In HTR-PM, besides the regular V&V similar to other NPPs, the interference effect of the alarm rings of the two reactor modules at the same time, and the potential discomfort of the two reactor operators after shift between them are focused. Verifications at early stage of the two issues are carried on the verification platform of the control room before the integrated system validation (ISV), and all the human machine interfaces (HMIs) in the control room, including the alarm system are validated in ISV. The test results on the verification platform show that the alarm displays and rings can support the operators understand the alarm information without confusion of the two reactors, and the shift between the two reactor operators have no adverse impact on operation. The results in ISV also show that the alarm system can support the operators well.

scholarly journals The Design of Turbomachinery for the Gas Turbine (Direct Cycle) High Temperature Gas Cooled Reactor Power Plant

1977 ◽  
Author(s):  
R. G. Adams ◽  
F. H. Boenig
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Gas Turbine ◽  
Power Conversion ◽  
Reactor Power ◽  
Working Fluid ◽  
Primary Coolant ◽  
Reactor Power Plant ◽  
Direct Cycle ◽  
High Temperature Gas

The Gas Turbine HTGR, or “Direct Cycle” High-Temperature Gas-Cooled, Reactor power plant, uses a closed-cycle gas turbine directly in the primary coolant circuit of a helium-cooled high-temperature nuclear reactor. Previous papers have described configuration studies leading to the selection of reactor and power conversion loop layout, and the considerations affecting the design of the components of the power conversion loop. This paper discusses briefly the effects of the helium working fluid and the reactor cooling loop environment on the design requirements of the direct-cycle turbomachinery and describes the mechanical arrangement of a typical turbomachine for this application. The aerodynamic design is outlined, and the mechanical design is described in some detail, with particular emphasis on the bearings and seals for the turbomachine.

Development of Key Technologies for the Next Generation High Temperature Gas Turbine

2011 ◽  
Author(s):  
Eisaku Ito ◽  
Ikuo Okada ◽  
Keizo Tsukagoshi ◽  
Junichiro Masada
Keyword(s):  
Global Warming ◽  
High Temperature ◽  
Power Plant ◽  
Gas Turbine ◽  
Thermal Efficiency ◽  
Reducing Power ◽  
Combined Cycle ◽  
National Project ◽  
Key Technologies ◽  
High Temperature Gas

Global warming is being “prevented” by reducing power plant CO2 emissions. We are contributing to the overall solution by improving the gas turbine thermal efficiency for gas turbine combined cycle (GTCC). Mitsubishi Heavy Industries, Ltd. (MHI) is a participant in a national project aimed at developing 1700°C gas turbine technology. As part of this national project, selected component technologies are investigated in detail. Some technologies which have been verified through component tests have been applied to the design of the newly developed 1600°C J-type gas turbine.

scholarly journals Gas Turbine Power Plant Possibilities With a Nuclear Heat Source: Closed and Open Cycles

1990 ◽  
Author(s):  
Colin F. McDonald
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Heat Source ◽  
Gas Turbine ◽  
Gas Turbines ◽  
Combined Cycle ◽  
Closed Cycle ◽  
Cycle System ◽  
Nuclear Heat ◽  
High Temperature Gas

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.

scholarly journals Analysis of a High Temperature Gas-Cooled Reactor Powered High Temperature Electrolysis Hydrogen Plant

2010 ◽  
Author(s):  
M. G. McKellar ◽  
E. A. Harvego ◽  
A. M. Gandrik
Keyword(s):  
High Temperature ◽  
Hydrogen Production ◽  
Economic Analysis ◽  
Electric Power ◽  
Production Rate ◽  
Production Plant ◽  
System Pressure ◽  
Reference Design ◽  
High Temperature Gas ◽  
High Temperature Electrolysis

An updated reference design for a commercial-scale high-temperature electrolysis (HTE) plant for hydrogen production has been developed. The HTE plant is powered by a high-temperature gas-cooled reactor (HTGR) whose configuration and operating conditions are based on the latest design parameters planned for the Next Generation Nuclear Plant (NGNP). The current HTGR reference design specifies a reactor power of 600 MWt, with a primary system pressure of 7.0 MPa, and reactor inlet and outlet fluid temperatures of 322°C and 750°C, respectively. The reactor heat is used to produce heat and electric power for the HTE plant. A Rankine steam cycle with a power conversion efficiency of 44.4% was used to provide the electric power. The electrolysis unit used to produce hydrogen includes 1.1 million cells with a per-cell active area of 225 cm2. The reference hydrogen production plant operates at a system pressure of 5.0 MPa, and utilizes a steam-sweep system to remove the excess oxygen that is evolved on the anode (oxygen) side of the electrolyzer. The overall system thermal-to-hydrogen production efficiency (based on the higher heating value of the produced hydrogen) is 42.8% at a hydrogen production rate of 1.85 kg/s (66 million SCFD) and an oxygen production rate of 14.6 kg/s (33 million SCFD). An economic analysis of this plant was performed with realistic financial and cost estimating The results of the economic analysis demonstrated that the HTE hydrogen production plant driven by a high-temperature helium-cooled nuclear power plant can deliver hydrogen at a competitive cost. A cost of $3.03/kg of hydrogen was calculated assuming an internal rate of return of 10% and a debt to equity ratio of 80%/20% for a reactor cost of $2000/kWt and $2.41/kg of hydrogen for a reactor cost of $1400/kWt.

Design and Development of HTR-PM Reactor Protection System

2013 ◽  
Author(s):  
Duo Li ◽  
Huasheng Xiong ◽  
Chao Guo
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
System Reliability ◽  
Nuclear Power ◽  
Protection System ◽  
Common Cause ◽  
Common Cause Failure ◽  
Plant Reactor ◽  
Reactor Protection System ◽  
High Temperature Gas

High Temperature gas-cooled Reactor-Pebble bed Module (HTR-PM) Reactor Protection System (RPS) is a dedicated system to be designed and developed according to HTR-PM Nuclear Power Plant reactor protection specifications. HTR-PM RPS has the framework of four redundant channels and has two independent and diverse subsystem x and subsystem y to perform different protection functions, which would decrease the potential common cause failure caused by software and increase the system reliability.

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