학술논문

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발행년	- (예 : 2010-2015)

Assessment of subchannel code ASSERT-PV for flow-distribution predictions

Academic Journal

Nava-Dominguez, A.; Rao, Y.F.; Waddington, G.M.

In Nuclear Engineering and Design August 2014 275:122-132

Full Text (ScienceDirect) Web of Science JCR 저널정보 Scopus Find it@PNU

ASSERT-PV 3.2: Advanced subchannel thermalhydraulics code for CANDU fuel bundles

Academic Journal

Rao, Y.F.; Cheng, Z.; Waddington, G.M.; Nava-Dominguez, A.

In Nuclear Engineering and Design August 2014 275:69-79

Full Text (ScienceDirect) Web of Science JCR 저널정보 Scopus Find it@PNU

Initial Multidisciplinary Study of Oxidized Chromium-Coated Zirconium Alloy for Fuel Cladding of SCW-SMR Concept: Weight-Gain and Thermal Conductivity Measurements and Coating Cost Evaluation

Academic Journal

Khumsa-Ang, K.; Mendoza, A.; Nava-Dominguez, A.; Azih, C.; Zahlan, H.

In: Coatings. (Coatings, September 2023, 13(9))

Full Text (Gale Academic Onefile) Full Text (ProQuest Central) Open Access (EBSCO) Web of Science JCR 저널정보 Scopus Find it@PNU

Steady-State Subchannel Thermal-Hydraulic Assessment of Advanced Uranium-Based and Thorium-Based Fuel Bundle Concepts for Potential Use in Pressure Tube Heavy Water Reactors

Academic Journal

Nava-Dominguez, A.; Liu, S.; Beuthe, T.; Bromley, B.P.; Colton, A.V.

In: Nuclear Technology. (Nuclear Technology, 2021, 207(8):1216-1236)

Web of Science JCR 저널정보 Scopus Find it@PNU

Evaluation of friction-factor correlations at supercritical water conditions in support of the Canadian SCWR

Academic Journal

Nava-Dominguez, A.

In: Journal of Nuclear Engineering and Radiation Science. (Journal of Nuclear Engineering and Radiation Science, July 2020, 6(3))

Web of Science JCR 저널정보 Scopus Find it@PNU

Thermal-hydraulics program in support of canadian SCWR concept development

Academic Journal

Leung, L.K.H.; Nava-Dominguez, A.

In: Journal of Nuclear Engineering and Radiation Science. (Journal of Nuclear Engineering and Radiation Science, January 2018, 4(1))

Web of Science JCR 저널정보 Scopus Find it@PNU

Assessment of subchannel code assert-PV for flow-distribution predictions

Conference

Nava-Dominguez, A.; Rao, Y.F.; Waddington, G.M.

In: International Conference on Nuclear Engineering, Proceedings, ICONE, 2013 21st International Conference on Nuclear Engineering, ICONE 2013. (International Conference on Nuclear Engineering, Proceedings, ICONE, 2013, 4)

Scopus Find it@PNU

Assert-PV 3.2: Improved subchannel thermalhydraulics code for candu fuel bundles

Conference

Rao, Y.F.; Cheng, Z.; Waddington, G.M.; Nava-Dominguez, A.

In: International Conference on Nuclear Engineering, Proceedings, ICONE, 2013 21st International Conference on Nuclear Engineering, ICONE 2013. (International Conference on Nuclear Engineering, Proceedings, ICONE, 2013, 4)

Scopus Find it@PNU

Development of an internally cooled annular fuel bundle for pressurized heavy water reactors

Conference

Hamilton, H.; Armstrong, J.; Kittmer, A.; Zhuchkova, A.; Xu, R.; Hyland, B.; King, M.; Nava-Dominguez, A.; Livingstone, S.; Bergeron, A.

In: International Nuclear Fuel Cycle Conference, GLOBAL 2013: Nuclear Energy at a Crossroads, International Nuclear Fuel Cycle Conference, GLOBAL 2013: Nuclear Energy at a Crossroads. (International Nuclear Fuel Cycle Conference, GLOBAL 2013: Nuclear Energy at a Crossroads, 2013, 2:1087-1096)

Scopus Find it@PNU

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