Numerical simulation of sodium-water reaction products transport in steam generator of Liquid Metal Fast Breeder Reactor on small water/steam leak

Citation
R. Duan et al., Numerical simulation of sodium-water reaction products transport in steam generator of Liquid Metal Fast Breeder Reactor on small water/steam leak, J NUC SCI T, 38(7), 2001, pp. 527-532
Citations number
9
Categorie Soggetti
Nuclear Emgineering
Journal title
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY
ISSN journal
00223131 → ACNP
Volume
38
Issue
7
Year of publication
2001
Pages
527 - 532
Database
ISI
SICI code
0022-3131(200107)38:7<527:NSOSRP>2.0.ZU;2-M
Abstract
The paper presents a three-dimensional model of sodium-water reaction produ ct transport in steam generators with a small water/steam leak. The model i s used to study the effects of thermodynamic parameters of steam generators of Liquid Metal Fast Breeder Reactor (LMFBR) on the leak response of a sma ll water leak detection system and to optimize the leak detection system de sign. A hydrogen gas line density concept is used to develop the differenti al equation of hydrogen ion transport. The model can be applied to analyze the leak response of hydrogen meters, oxygen meters and other concentration -type leak detection systems. The model was verified with water injections into sodium with different temperatures in a simple sodium loop with a hydr ogen meter.