Development and application of a comprehensive model of a lead-cooled fast reactor using the FAST code system

Yancey K, Mikityuk K, Krepel J & Chenu A
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Yancey, K., Mikityuk, K., Krepel, J., & Chenu, A. (2011). Development and application of a comprehensive model of a lead-cooled fast reactor using the FAST code system. In Transactions of the American Nuclear Society: Vol. 105. Winter meeting 2011 (pp. 699-700).