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Gray, D.L.; Harkins, C.K.; Hoole, J.G.
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] Traditionally, there has been a very high learning curve associated with using nuclear power plant (NPP) analysis codes. Even for seasoned plant analysts and engineers, the process of building or modifying an input model for present day NPP analysis codes is tedious, error prone, and time consuming. Current cost constraints and performance demands place an additional burden on today's safety analysis community. Advances in graphical user interface (GUI) technology have been applied to obtain significant productivity and quality assurance improvements for the Transient Reactor Analysis Code (TRAC) input model development. KAPL Inc. has developed an X Windows-based graphical user interface named TOOKUIL which supports the design and analysis process, acting as a preprocessor, runtime editor, help system, and post processor for TRAC. This paper summarizes the objectives of the project, the GUI development process and experiences, and the resulting end product, TOOKUIL
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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. 698-715; 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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