Computational Analysis of the Thermal-Hydraulic Characteristics of the Encapsulated Nuclear Heat Source

2005 ◽  
Vol 152 (3) ◽  
pp. 324-338 ◽  
Author(s):  
Yoshihisa Nishi ◽  
Nobuyuki Ueda ◽  
Izumi Kinoshita ◽  
Ehud Greenspan
Keyword(s):  
Heat Source ◽  
Computational Analysis ◽  
Hydraulic Characteristics ◽  
Nuclear Heat

Modeling and Analysis of Power Conversion System for High Temperature Gas Cooled Reactor With Cogeneration

2008 ◽  
Author(s):  
Ali Afrazeh ◽  
Hiwa Khaledi ◽  
Mohammad Bagher Ghofrani
Keyword(s):  
High Temperature ◽  
Heat Source ◽  
Gas Turbine ◽  
Power Conversion ◽  
Hot Water ◽  
Working Fluid ◽  
Closed Cycle ◽  
Nuclear Heat ◽  
Conversion System ◽  
High Temperature Gas

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.

Selecting a distillation scheme for purifying ditolylmethane for a nuclear heat source

1988 ◽  
Vol 65 (2) ◽  
pp. 692-695
Author(s):  
V. I. Garanin ◽  
G. F. Stychinskii ◽  
G. Z. Chukhlov ◽  
V. S. Smirnova
Keyword(s):  
Heat Source ◽  
Nuclear Heat

Inherently Safe Nuclear Power Generation With Electrically Coupled Compressor and Turbo Expander(s)

2004 ◽  
Author(s):  
Gulian A. K. Crommelin ◽  
Walter F. Crommelin
Keyword(s):  
Power Generation ◽  
Heat Source ◽  
Gas Turbine ◽  
Gas Turbines ◽  
Nuclear Power ◽  
Small Scale ◽  
Nuclear Power Generation ◽  
Small Current ◽  
Nuclear Heat ◽  
Open Cycle

Gas turbines in combination with a nuclear heat source have been subject for study for some years. This paper is a logical follow up on previous papers regarding small scale nuclear power generation using gas turbines with a well-proven, inherently safe nuclear heat source. In the Netherlands the NEREUS project has been working on this concept since 1993. The acronym NEREUS describes very well the goals of this project. (Ref 1, 2, 3, 4, 5). NEREUS stands for: a Natural safe, Efficient, Reactor, Easy to operate, Ultimately simple and Small. Current studies focus on the gas turbine part of the installation. After three years of studying the possibilities of the closed cycle helium gas turbine, the NEREUS project returned in 2000 to its original thought of using an existing open-cycle gas turbine or components of such an engine, as energy conversion unit. The paper starts with an introduction on why nuclear power should get more attention, basically explaining “the reasons why” of the NEREUS project. Secondly the paper gives an overview of the main characteristics of the nuclear heat source. Thirdly the paper will discuss the current study to determine the specifications of an open-cycle gas turbine for the NEREUS installation. Attention is given to the way such an open-cycle gas turbine can be controlled. The nuclear heat source is controlled by the laws of physics and it is not recommended to intervene under any circumstances with this very important safety feature.

Analysis of a 115MW, 3-Shaft, Helium Brayton Cycle Using Nuclear Heat Source

2001 ◽  
Author(s):  
K. Pradeep Kumar ◽  
A. Tourlidakis ◽  
P. Pilidis
Keyword(s):  
Steady State ◽  
Performance Analysis ◽  
Heat Source ◽  
Absolute Pressure ◽  
Brayton Cycle ◽  
Shaft Speed ◽  
Closed Cycle ◽  
Surge Margin ◽  
Nuclear Heat ◽  
Steady State Performance

This paper describes the steady state performance analysis of a 3-shaft closed cycle helium turbine using nuclear heat source. The analysis is carried out using a computer program, which is specifically made for this cycle. The computer model was tested for various Turbine Entry Temperatures (TET) and absolute pressures. The analysis of the change was focused on the compressors, as these are relatively more critical than the rest of the equipments. The change in TET triggered changes in shaft speed, mass flow rate, power output, absolute pressure etc. Adjustable guide vanes were used to study the operation with constant surge margin. The closed cycle was tested for various absolute pressures and it was established that the efficiency will not be affected in using the inventory control for the load variation.

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