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H.Tanab*; Miyake, Osamu*; M.hori*; Y.Ohmor*; Daigo, Y.*; Sato, Minoru*; T.Takah*
PNC TN943 81-02, 25 Pages, 1981/01
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M.hori*; Miyake, Osamu*
PNC TN941 80-91, 28 Pages, 1980/07
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Miyake, Osamu*; Shindo, Yoshihisa*; Sato, Minoru*
PNC TN952 79-20Tr, 76 Pages, 1979/09
A computer code, SWACS, has been developed for analyzing a large-scale sodium-water reaction accident in a steam generator system of LMFBRs. The SWACS integrated code system is capable of predicting the principal events relevant to the large-scale water leak accident in the steam generator of LMFBRs: leaking flow of water/steam mixture from a ruptured heat-transfer tube into sodium in any one of the steam generators; propagation of pressure wave generated by sodium-water reaction both within the faulted steam generator and into the secondary cooling system ; and hydraulic transients induced in the secondary cooling circuit and reaction relief system. The water/steam leaks postulated in the SWACS code are, in principle, equivalent to those from the breach of one double-ended (guillotine) rupture of heat-transfer tube. This report is an input manual of the SWACS code and describes the structure of SWACS, input/output format and sample cases for demonstration. It is to be noted that a companion volume (PNC SN952-79-19) explains the underlying models and numerical methods adopted in the SWACS code.
Miyake, Osamu*; Shindo, Yoshihisa*; Sato, Minoru*
PNC TN952 79-19TR, 44 Pages, 1979/09
A computer code, SWACS, has been developed for analyzing a large-scale sodium-water reaction accident in a steam generator system of LMFBRs. The SWACS integrated code system is capable of predicting the principal events relevant to the large-scale water leak accident in the steam generator of LMFBRs: leaking flow of water/steam mixture from a ruptured heat-transfer tube into sodium in any one of the steam generators; propagation of pressure wave generated by sodium-water reaction both within the faulted steam generator and into the secondary cooling system ; and hydraulic transients induced in the secondary cooling circuit and reaction relief system. The water/steam leaks postulated in the SWACS code are, in principle, equivalent to those from the breach of one double-ended (guillotine) rupture of heat-transfer tube. This report summarizes the underlying models and numerical methods adopted in the SWACS code. It is to be noted that a companion volume (PNC SN952 79-20) may serve as an input manual for users. SWACS contains and controls the following three prenomenological modules SWAC-11, -5K/7 and -13: (1)SWAC-11 is the module for analyzing the water-side transients and the leaking flow of water/steam mixture into sodium of a faulted steam generator. Fundamental equations are one-dimensional mass, momentum and energy conservation for either subcooled or saturated water, or superheated steam. The two phase flow is assumed to be homogeneous (non-slip) flow in thermal equilibrium between the two phases. Compressibility of the fluid is considered for accounting the rapid transient of the water/steam flow in the very early stage of tube rupture. Boundary conditions are imposed at the inlet and outlet headers of water loop and the openings of the ruptured heat-transfer tube. The back pressure at the openings is taken as the pressure of reaction zone which is provided by the SWAC-5K/7 module. (2)SWAC-5K/7 analyzes the behavior of rapid pressure transient, called ...
