Author:
Bagdasarov Yu. E.,Bogoslovskaya G. P.,Zhukov A. V.,Ivanov E. F.,Sorokin A. P.,Kolesnik V. P.,Ushakov P. A.
Publisher
Springer Science and Business Media LLC
Subject
Nuclear Energy and Engineering
Reference4 articles.
1. F. Hubert, "Loss of flow experiments in sodium in an electrically heated 37-pin bundle with sinusoidal acial heat flux distribution," ibid., pp. 341–349.
2. F. Hubert and W. Peppler, "Boiling and dry out behind local blockages in sodium cooled rod bundles," Nucl. Engng. Design,82, No. 3, 341–363 (1984).
3. J. Sealer, G. Cognet, E. Leborque, et al., "French LMFBR core thermal hydraulic studies for nominal and accident conditions," ibid.,,124, No. 3, 403–416 (1990).
4. O. Dwyer, "Incipient boiling superheat for sodium in turbulent channel flow effects of heat flux and flow rate," J. Heat and Mass Transfer,16, No. 5, 971–984 (1973).