The Next Generation Nuclear Plant (NGNP) Project is a US-based initiative led by Idaho National Laboratories to demonstrate the viability of using High Temperature Gas-Cooled Reactor (HTGR) technology for the production of high temperature steam and/or heat for applications such as heavy oil recovery, process steam/cogeneration and hydrogen production. A key part of the NGNP Project is the development of a Component Test Facility (CTF) that will support the development of high temperature gas thermal-hydraulic technologies as applied in heat transport and heat transfer applications in HTGRs. These applications include, but are not limited to, primary and secondary coolants, direct cycle power conversion, co-generation, intermediate, secondary and tertiary heat transfer, demonstration of processes requiring high temperatures as well as testing of NGNP specific control, maintenance and inspection philosophies and techniques. The feasibility of the envisioned CTF as a development and testing platform for components and systems in support of the NGNP was evaluated. For components and systems to be integrated into the NGNP full scale or at least representative size tests need to be conducted at NGNP representative conditions, with regards to pressure, flow rate and temperature. Typical components to be tested in the CTF include heat exchangers, steam generators, circulators, valves and gas piping. The Design Data Needs (DDNs), Technology Readiness Levels (TRLs) as well as Design Readiness Levels (DRLs) prepared in the pre-conceptual design of the NGNP Project and the NGNP lifecycle requirements were used as inputs to establish the CTF Functional and Operating Requirements (F&ORs). The existing South African PBMR test facilities were evaluated to determine their current applicability or possible modifications to meet the F&ORs of the CTF. Three concepts were proposed and initial energy balances and layouts were developed. This paper will present the results of this CTF study and the ongoing efforts to establish the CTF.
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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:
978-0-7918-4855-5
PROCEEDINGS PAPER
HTGR Component Test Facility (CTF) Feasibility Study for NGNP
Jan P. van Ravenswaay,
Jan P. van Ravenswaay
M-Tech Industrial (Pty.) Ltd., Potchefstroom, North-West, South Africa
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Jacques Holtzhausen,
Jacques Holtzhausen
M-Tech Industrial (Pty.) Ltd., Potchefstroom, North-West, South Africa
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Jaco van der Merwe,
Jaco van der Merwe
M-Tech Industrial (Pty.) Ltd., Potchefstroom, North-West, South Africa
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Kobus Olivier,
Kobus Olivier
M-Tech Industrial (Pty.) Ltd., Potchefstroom, North-West, South Africa
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Riaan du Bruyn,
Riaan du Bruyn
M-Tech Industrial (Pty.) Ltd., Potchefstroom, North-West, South Africa
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Andries Haasbroek,
Andries Haasbroek
Westinghouse Electric South Africa (Pty.) Ltd., Centurion, Gauteng, South Africa
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Marius Fox
Marius Fox
Westinghouse Electric South Africa (Pty.) Ltd., Centurion, Gauteng, South Africa
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Jan P. van Ravenswaay
M-Tech Industrial (Pty.) Ltd., Potchefstroom, North-West, South Africa
Jacques Holtzhausen
M-Tech Industrial (Pty.) Ltd., Potchefstroom, North-West, South Africa
Jaco van der Merwe
M-Tech Industrial (Pty.) Ltd., Potchefstroom, North-West, South Africa
Kobus Olivier
M-Tech Industrial (Pty.) Ltd., Potchefstroom, North-West, South Africa
Riaan du Bruyn
M-Tech Industrial (Pty.) Ltd., Potchefstroom, North-West, South Africa
Andries Haasbroek
Westinghouse Electric South Africa (Pty.) Ltd., Centurion, Gauteng, South Africa
Marius Fox
Westinghouse Electric South Africa (Pty.) Ltd., Centurion, Gauteng, South Africa
Paper No:
HTR2008-58214, pp. 381-390; 10 pages
Published Online:
July 1, 2009
Citation
van Ravenswaay, JP, Holtzhausen, J, van der Merwe, J, Olivier, K, du Bruyn, R, Haasbroek, A, & Fox, M. "HTGR Component Test Facility (CTF) Feasibility Study for NGNP." Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology. Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2. Washington, DC, USA. September 28–October 1, 2008. pp. 381-390. ASME. https://doi.org/10.1115/HTR2008-58214
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