http://www.loc.gov/mods/v3 http://www.loc.gov/standards/mods/v3/mods-3-2.xsd
Dynamic system characterization of an integral test facility of an advanced PWR
Dynamic system characterization of an integral test facility of an advanced pressurized water reactor
analysis. These equations were used for the linear analysis
and actuators for its safety functions. The inclusion of
and their topology, as they are used to characterize such a
any conventional pressurized water reactor, in which the
assessment against AP600 relevant phenomena. The AP600
bond graph methodology was used to formulate the equations
complex system. This characterization was applied to one of
Core Makeup Tanks and passive heat removal systems into the
design increase its dynamic complexity well beyond that of
design relies only on passive safety features such as gravity
driven draining pressurized tanks, and battery power logic
equations were linearized for a selected period of the
Large Scale Test Facility (LSTF), which has been selected by
mathematical model of the system. The model's constitutive
one-inch cold leg break (AP-CL-03), to construct a
performing a series of tests to generate data for code
safeties can be treated as imposed boundary conditions. The
testing of the Westinghouse AP600 design. The LSTF is
the Rig of Safety Assessment (ROSA) program transients, the
the U.S. Nuclear Regulatory Commission for confirmatory
This work characterizes the dynamic behavior for the modified
transient that is of particular importance to the safety
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