[en] A computer code for modeling Liquid Metal Fast Breeder Reactor (LMFBR) Steam Generator (SG) leaks has been partially validated. This was accomplished by comparing code results with data from large leak Sodium/Water Reaction (SWR) tests conducted at the Energy Technology Engineering Center (ETEC). In each of six tests, a Double-Ended Guillotine (DEG) rupture of an SG tube was produced in a sodium-filled SG at typical operating conditions. The primary purpose of these tests was to provide data for validation of the TRANSWRAP (Transient Sodium Water Reaction Analysis Program) code. Primary areas of concern are the leaksite pressure history, pressures at various locations throughout the system, and expulsion of reaction products through the relief system. Agreement with TRANSWRAP results was found to be remarkably good