An analysis of the pressure wave propagation by the sodium-water reaction in the printed circuit steam generator using the SWAAM-II code. (15th December 2022)

• Record Type: Journal Article
• Authors: Kim, Taewoo; Kim, Sang Ji
• Is Part Of: Annals of nuclear energy. Volume 179(2022)
• Publication Date: 2022-12-15
• Subjects: Printed Circuit Steam Generator -- Pressure wave -- Sodium-Water Reaction -- SWAAM-II; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2022.109423
• Languages: English
• ISSNs: 0306-4549

Abstract

Abstract: The Sodium-Water Reaction (SWR) is the biggest problem for the development of the steam generator (SG) of the Sodium-cooled Fast Reactor (SFR). The pressure wave generation by the SWR has effects on the structural integrity of the Intermediate Heat Transport System (IHTS). However, when the Printed Circuit Steam Generator (PCSG) is used, the safety of SFR is expected to be improved. Since the PCSG is composed of a millimeter size of flow channels, the SWR zone is limited to the small channel. Therefore, it is necessary to evaluate the pressure spike and propagation in the PCSG. In this study, the SWAAM-II is used to analyze the pressure wave transfer by the SWR when the PCSG is used. The pressure in the sodium channel suddenly increases when the SWR occurs and the high pressure wave is transferred towards the headers. The peak pressure in the sodium channel is 16 MPa which is 21 % of the allowable stress based on the design by rule. However, the pressure wave is attenuated in the header due to the large difference in the cross-section area between the sodium channel and header. When it is assumed that the SWR occurs in the header, the pressure in the IHTS is increased. However, the increase of pressure in the IHTS is much less than the case of in the shell and tube type SG.