Thermal-hydraulic issues and achievements – A historical perspective

Author:

Yadigaroglu G.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference75 articles.

1. Influence of axial power distribution on dryout: film-flow models and experiments;Adamsson;Nucl. Eng. Design,2010

2. Phenomenological modeling of critical heat flux: The GRAMP code and its validation;Ahmad;Nucl. Eng. Design,2013

3. User effects on the thermal-hydraulic transient system code calculations;Aksan;Nucl. Eng. Design,1993

4. Andersson, S., Stepniewski, M., Assessment of RAMONA-3B Calculations of Core-Wide and Regional Power/Flow Oscillations – Comparison with Oskarshamm-3 Natural Circulation Test Data, pp. 397-411 in Int. Workshop on Boiling Water Reactor Stability, Proceedings, Holtsville, New York, 17-19 October 1990, CSNI Report 178, OECD Nuclear Energy Agency, Paris.

5. CFD Modeling of Boiling Annular-Mist Flow for Dryout Investigations;Anglart;Multiph. Sci. Technol.,2011

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