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Luxat, J.C.; Liu, W.S.; Leung, R.K.
Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements1997
Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements1997
AbstractAbstract
[en] An overview is presented of the Canadian two-fluid computer codes TUF and CATHENA with specific focus on the constraints imposed during development of these codes and the areas of application for which they are intended. Additionally a process for systematic assessment of these codes is described which is part of a broader, industry based initiative for validation of computer codes used in all major disciplines of safety analysis. This is intended to provide both the licensee and the regulator in Canada with an objective basis for assessing the adequacy of codes for use in specific applications. Although focused specifically on CANDU reactors, Canadian experience in developing advanced two-fluid codes to meet wide-ranging application needs while maintaining past investment in plant modelling provides a useful contribution to international efforts in this area
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Ebert, D.; Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; Nuclear Energy Agency, 75 - Paris (France); SCIENTECH, Inc., Boise, ID (United States); 824 p; Jul 1997; p. 94-111; Organization for Economic Co-Operation and Development (OECD)/Committee on the Safety of Nuclear Installations (CSNI) workshop on transient thermal-hydraulic codes requirements; Annapolis, MD (United States); 5-8 Nov 1996; Also available from OSTI as TI97008508; NTIS; GPO
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Report
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Conference
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