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.
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Fourth International Topical Meeting on High Temperature Reactor Technology
September 28–October 1, 2008
Washington, DC, USA
Conference Sponsors:
- ASME
ISBN:
978-0-7918-4854-8
PROCEEDINGS PAPER
Design Option of Heat Exchanger for the Next Generation Nuclear Plant
Chang H. Oh,
Chang H. Oh
Idaho National Laboratory, Idaho Falls, ID
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Eung S. Kim
Eung S. Kim
Idaho National Laboratory, Idaho Falls, ID
Search for other works by this author on:
Chang H. Oh
Idaho National Laboratory, Idaho Falls, ID
Eung S. Kim
Idaho National Laboratory, Idaho Falls, ID
Paper No:
HTR2008-58175, pp. 697-707; 11 pages
Published Online:
July 1, 2009
Citation
Oh, CH, & Kim, ES. "Design Option of Heat Exchanger for the Next Generation Nuclear Plant." Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology. Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 1. Washington, DC, USA. September 28–October 1, 2008. pp. 697-707. ASME. https://doi.org/10.1115/HTR2008-58175
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