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Research Papers: Nuclear Power

Design Option of Heat Exchanger for the Next Generation Nuclear Plant

[+] Author and Article Information
Chang H. Oh, Eung S. Kim, Mike Patterson

 Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415

J. Eng. Gas Turbines Power 132(3), 032903 (Dec 01, 2009) (9 pages) doi:10.1115/1.3126780 History: Received December 03, 2008; Revised December 05, 2008; Published December 01, 2009; Online December 01, 2009

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.

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References

Figures

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Figure 6

Maximum stress as a function of plate thickness-to-diameter ratio (PCHE, 900°C)

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Figure 7

Maximum stress as a function of tube thickness-to-radius ratio (shell-and-tube, 900°C)

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Figure 5

Comparisons of biaxial strength data with failure theories (15)

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Figure 4

Smt (MPa) versus lifetime (h) for Alloy 617

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Figure 3

Design conditions for two-stage IHX

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Figure 2

Reference VHTR system (indirect parallel configuration (11))

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Figure 1

Cross section through a typical PCHE core (Courtesy of Heatric Ltd.)

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