NDLI: HTGR Component Test Facility (CTF) Feasibility Study for NGNP

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Jan, P. Van Ravenswaay Holtzhausen, Jacques Merwe, Jaco Van Der Olivier, Kobus Bruyn, Riaan Du Haasbroek, Andries Fox, Marius
Copyright Year	2008
Abstract	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.
Starting Page	381
Ending Page	390
Page Count	10
File Format	PDF
ISBN	9780791848555
DOI	10.1115/HTR2008-58214
e-ISBN	9780791838341
Volume Number	Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2
Conference Proceedings	Fourth International Topical Meeting on High Temperature Reactor Technology
Language	English
Publisher Date	2008-09-28
Publisher Place	Washington, DC, USA
Access Restriction	Subscribed
Subject Keyword	Cycles Test facilities Temperature Valves High temperature Design Energy conversion Coolants Petroleum extraction Testing Inspection Boilers Heat exchangers Maintenance Combined heat and power Flow (dynamics) Pressure High temperature steam Heat Very high temperature reactors Steam Nuclear power stations Pipes Heat transfer Hydrogen production
Content Type	Text
Resource Type	Article

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