scholarly journals Design Option of Heat Exchanger for the Next Generation Nuclear Plant

2008 ◽  
Author(s):  
Chang H. Oh ◽  
Eung S. Kim
Keyword(s):  
Heat Exchanger ◽  
System Integration ◽  
Power Conversion ◽  
Nuclear Plant ◽  
Design And Technology ◽  
Production Plant ◽  
Next Generation ◽  
Tube Heat Exchanger ◽  
Intermediate Heat Exchanger ◽  
Hydrogen Plant

The Next Generation Nuclear Plant (NGNP), a very High temperature Gas-Cooled Reactor (VHTR) concept, will provide the first demonstration of a closed-loop Brayton cycle at a commercial scale, producing a few hundred megawatts of power in the form of electricity and hydrogen. The power conversion unit (PCU) for the NGNP will take advantage of the significantly higher reactor outlet temperatures of the VHTRs to provide higher efficiencies than can be achieved with the current generation of light water reactors. Besides demonstrating a system design that can be used directly for subsequent commercial deployment, the NGNP will demonstrate key technology elements that can be used in subsequent advanced power conversion systems for other Generation IV reactors. In anticipation of the design, development and procurement of an advanced power conversion system for the NGNP, the system integration of the NGNP and hydrogen plant was initiated to identify the important design and technology options that must be considered in evaluating the performance of the proposed NGNP. As part of the system integration of the VHTRs and the hydrogen production plant, the intermediate heat exchanger is used to transfer the process heat from VHTRs to the hydrogen plant. Therefore, the design and configuration of the intermediate heat exchanger is very important. This paper will include analysis of one stage versus two stage heat exchanger design configurations and simple stress analyses of a printed circuit heat exchanger (PCHE), helical coil heat exchanger, and shell/tube heat exchanger.

scholarly journals Design Option of Heat Exchanger for the Next Generation Nuclear Plant

2009 ◽  
Vol 132 (3) ◽  
Author(s):  
Chang H. Oh ◽  
Eung S. Kim ◽  
Mike Patterson
Keyword(s):  
Heat Exchanger ◽  
System Integration ◽  
Power Conversion ◽  
Nuclear Plant ◽  
Design And Technology ◽  
Production Plant ◽  
Next Generation ◽  
Tube Heat Exchanger ◽  
Intermediate Heat Exchanger ◽  
Hydrogen Plant

The next generation nuclear plant (NGNP), a very high temperature gas-cooled reactor (VHTR) concept, will provide the first demonstration of a closed-loop Brayton cycle at a commercial scale, producing a few hundred megawatts of power in the form of electricity and hydrogen. The power conversion unit for the NGNP will take advantage of the significantly higher reactor outlet temperatures of the VHTRs to provide higher efficiencies than can be achieved with the current generation of light water reactors. Besides demonstrating a system design that can be used directly for subsequent commercial deployment, the NGNP will demonstrate key technology elements that can be used in subsequent advanced power conversion systems for other Generation IV reactors. In anticipation of the design, development, and procurement of an advanced power conversion system for the NGNP, the system integration of the NGNP and hydrogen plant was initiated to identify the important design and technology options that must be considered in evaluating the performance of the proposed NGNP. As part of the system integration of the VHTRs and the hydrogen production plant, the intermediate heat exchanger is used to transfer the process heat from VHTRs to the hydrogen plant. Therefore, the design and configuration of the intermediate heat exchanger are very important. This paper describes analyses of one stage versus two-stage heat exchanger design configurations and simple stress analyses of a printed circuit heat exchanger (PCHE), helical-coil heat exchanger, and shell-and-tube heat exchanger.

Design Configurations for Very High Temperature Gas-Cooled Reactor Designed to Generate Electricity and Hydrogen

2006 ◽  
Author(s):  
Chang H. Oh ◽  
Cliff Davis ◽  
Robert Barner ◽  
Steven Sherman
Keyword(s):  
High Temperature ◽  
Power Conversion ◽  
Design And Technology ◽  
Production Plant ◽  
Design Development ◽  
Working Fluids ◽  
Conversion System ◽  
Hydrogen Plant ◽  
Liquid Salts ◽  
High Temperature Gas

The High Temperature Gas-Cooled Reactor is being envisioned that will generate not just electricity, but also hydrogen to charge up fuel cells for cars, trucks and other mobile energy uses. INL engineers studied various heat-transfer working fluids—including helium and liquid salts—in seven different configurations. In computer simulations, serial configurations diverted some energy from the heated fluid flowing to the electric plant and hydrogen production plant. In anticipation of the design, development and procurement of an advanced power conversion system for HTGR, this study was initiated to identify the major design and technology options and their tradeoffs in the evaluation of power conversion system (PCS) coupled to hydrogen plant. In this study, we investigated a number of design configurations and performed thermal hydraulic analyses using various working fluids and various conditions (Oh, 2005). This paper includes a portion of thermal hydraulic results based on a direct cycle and a parallel intermediate heat exchanger (IHX) configuration option.

IHX Design and Development for the Next Generation Nuclear Plant

2008 ◽  
Author(s):  
Scott R. Penfield ◽  
Renee Greyvenstein ◽  
Phillip L. Rittenhouse ◽  
James Nash
Keyword(s):  
Technology Development ◽  
Nuclear Plant ◽  
Operating Conditions ◽  
Design And Technology ◽  
Next Generation ◽  
Thin Sections ◽  
Compact Heat Exchangers ◽  
Corrosion Rates ◽  
Intermediate Heat Exchanger

This paper summarizes the results of a conceptual design study addressing the design and technology development requirements for a high-temperature intermediate heat exchanger (IHX) for the Next Generation Nuclear Plant (NGNP). Results of the study confirmed the incentives for compact heat exchangers and suggested new IHX configurations that provide for maintainability at the heat transfer module level. Scoping analyses provided encouragement that IHX life would not be limited by creep or fatigue effects, given the PBMR NGNP Heat Transport System architecture and operating conditions. However, corrosion rates implied by existing data are troubling for thin sections, and improved characterization of environmental effects was identified as a high priority for technology development.

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