Ex-vessel boiling experiments: laboratory- and reactor-scale testing of the flooded cavity concept for in-vessel core retention Part I: Observation of quenching of downward-facing surfaces

Nuclear Engineering and Design - Tập 169 - Trang 77-88 - 1997
T.Y. Chu1, B.L. Bainbridge1, R.B. Simpson1, J.H. Bentz1
1Sandia National Laboratories, PO Box 5800, Albuquerque, NM 87185-1137, USA

Tài liệu tham khảo