Neutronic and thermohydraulic analysis of a SMR-PWR core with TRISO fuel based on a 2n multifactorial analysis

Author:

Rosales Jesús,François Juan-Luis,Ortiz Annie,García Carlos

Funder

Universidad Nacional Autónoma de México

National Autonomous University of Mexico Directorate General of Academic Staff Affairs

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

Reference33 articles.

1. ANSYS Inc., 2010. ANSYS CFX Solver Theory Guide. Canonsburg, PA.

2. Box, G.E., S., H.J., Hunter, W.G., 2008. Estadística para investigadores. Diseño, innovación y descubrimiento., 2nd ed. Barcelona.

3. Reactor physics analysis with Monte Carlo;Brown;Physor,2010

4. Canonsburg, T.D., 2013. ANSYS CFX-Pre User ’ s Guide 15317, 724–746.

5. Code of Federal Regulations, 2007. Acceptance criteria for emergency core cooling systems for light water nuclear power reactors. As Amend. 72 FR 49508.

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