The ceramic fuel and core, inert helium coolant and superior safety characteristics of the modular High-Temperature Gas-cooled Reactor (HTGR) are the bases for its potential to displace the fossil energy resources that are presently dominant in industrial process steam and cogeneration applications. In achieving this potential, a particular challenge is to provide a flexible and efficient coupling between the high-temperature HTGR heat source and various industrial processes. This challenge was addressed in the course of developing the conceptual design of the Steam Cycle-Modular Helium Reactor for the Next Generation Nuclear Plant (NGNP) Project. This paper characterizes the energy requirements of high-potential process steam and cogeneration applications and describes the development of a steam utilization architecture that can serve a wide range of industrial applications with superior flexibility and efficiency.
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2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference
July 30–August 3, 2012
Anaheim, California, USA
Conference Sponsors:
- Nuclear Engineering Division
- Power Division
ISBN:
978-0-7918-4495-3
PROCEEDINGS PAPER
Development of the Steam Cycle-Modular Helium Reactor Steam Utilization System for High-Efficiency Cogeneration Available to Purchase
Scott R. Penfield, Jr.
Scott R. Penfield, Jr.
Technology Insights, San Diego, CA
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Scott R. Penfield, Jr.
Technology Insights, San Diego, CA
Paper No:
ICONE20-POWER2012-55254, pp. 707-712; 6 pages
Published Online:
October 30, 2013
Citation
Penfield, SR, Jr. "Development of the Steam Cycle-Modular Helium Reactor Steam Utilization System for High-Efficiency Cogeneration." Proceedings of the 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance. Anaheim, California, USA. July 30–August 3, 2012. pp. 707-712. ASME. https://doi.org/10.1115/ICONE20-POWER2012-55254
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