Innovative radiation-based direct heat exchanger (DHX) for liquid metal cooled reactors

被引:9
作者
De Santis, Andrea [1 ]
Di Maio, Damiano Vitale [1 ]
Caruso, Gianfranco [1 ]
Manni, Fabio [2 ]
机构
[1] Univ Roma La Sapienza, DIAEE, I-00186 Rome, Italy
[2] SRS Serv Ric & Sviluppo Srl, Rome, Italy
关键词
REMOVAL SYSTEM; DESIGN; JAPAN; POOL; LEAD;
D O I
10.1016/j.nucengdes.2013.04.021
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Considering the importance of safety features in the development of Generation IV nuclear reactors, an innovative and passive decay heat removal system (DHRS) has been proposed for liquid metal cooled reactors. The attention is here focused on the direct heat exchanger (DHX) of the system constituted by a bayonet tube that allows to remove the decay heat from the primary coolant; both primary and secondary fluids flow in natural circulation. Since each bayonet tube is equipped with a vacuum gap, the most important heat transfer mechanism characterizing the DHX is radiation. Furthermore, the presence of the vacuum gap guarantees a physical separation and a complete decoupling between primary and secondary fluids, enhancing the safety features of the whole system. Several CFD analyses have been carried out in order to obtain a characterization of the DHX both for sodium and lead cooled fast reactors, in order to optimize the DHX geometry on the basis of the specific application, and the results are discussed in the paper. (c) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:164 / 171
页数:8
相关论文
共 14 条
[1]   European lead fast reactor-ELSY [J].
Alemberti, Alessandro ;
Carlsson, Johan ;
Malambu, Edouard ;
Orden, Alfredo ;
Struwe, Dankward ;
Agostini, Pietro ;
Monti, Stefano .
NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (09) :3470-3480
[2]  
Caruso G., 2012, INT J RISK THEORY, V2, P11
[3]  
De Santis A., 2012, P 30 UIT HEAT TRANSF
[4]   An innovative pool with a passive heat removal system [J].
Di Maio, Damiano Vitale ;
Naviglio, Antonio ;
Giannetti, Fabio ;
Manni, Fabio .
ENERGY, 2012, 45 (01) :296-303
[5]   Fast reactor decay heat removal:: approach to the safety system design in Japan and Europe [J].
Farrar, B ;
Lefèvre, JC ;
Kubo, S ;
Mitchell, CH ;
Yoshinari, Y ;
Itooka, S .
NUCLEAR ENGINEERING AND DESIGN, 1999, 193 (1-2) :45-54
[6]  
Fink J.K., 1995, ARGONNE NATL LAB PUB, P2
[7]   The present status of DFBR development in Japan [J].
Inagaki, T ;
Ueta, M ;
Hamada, M ;
Kobayashi, T .
PROGRESS IN NUCLEAR ENERGY, 1998, 32 (3-4) :281-288
[8]   European fast reactor design [J].
Lefevre, JC ;
Mitchell, CH ;
Hubert, G .
NUCLEAR ENGINEERING AND DESIGN, 1996, 162 (2-3) :133-143
[9]   Functional reliability analysis of Safety Grade Decay Heat Removal System of Indian 500 MWe PFBR [J].
Mathews, T. Sajith ;
Ramakrishnan, M. ;
Parthasarathy, U. ;
Arul, A. John ;
Kumar, C. Senthil .
NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (09) :2369-2376
[10]   Decay heat removal in pool type fast reactor using passive systems [J].
Parthasarathy, U. ;
Sundararajan, T. ;
Balaji, C. ;
Velusamy, K. ;
Chellapandi, P. ;
Chetal, S. C. .
NUCLEAR ENGINEERING AND DESIGN, 2012, 250 :480-499