V&V&C in nuclear reactor thermal-hydraulics

Author:

D'Auria Francesco,Lanfredini Marco

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

Reference40 articles.

1. FONESYS: the forum & network of SYStem thermal-hydraulic codes in nuclear reactor thermal-hydraulics;Ahn;Nucl. Eng. Des.,2015

2. Thermal-hydraulic phenomena for water cooled nuclear reactors;Aksan;Nucl. Eng. Des.,2018

3. 1990, Evaluation of Accuracy of Thermal-hydraulic Codes Calculations;Ambrosini;J. Energia Nucleare,1990

4. Ashley, R., El-Shanawany, M., Eltawila, F., D'Auria, F., 1998, Good Practices for User Effect Reduction, OECD/CSNI Report NEA/CSNI/R(98)22, Paris (F), Nov.

5. Berry, R.A., Peterson, J.W., Zhang, H., Martineau, R.C., Zhao, H., Zou, L., Andrs, D., 2015, RELAP-7 theory manual, INL/EXT-14-31366 (rev. 1), Idaho Falls (ID, USA).

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