Multinode analysis of small breaks for B and W's 145-fuel-assembly nuclear plants with internals vent valves. [PWR]

Multinode analyses were conducted for several small breaks in the reactor coolant system of B&W's 145 fuel-assembly nuclear plants with internals vent valves. The multinode blowdown code CRAFT was used to evaluate the hydrodynamics and transient water inventories of the reactor coolant system. The FOAM code was used to compute a swell level history for the core. and the THETA 1- B code was used to perform transient fuel pin thermal calculations. Curves showing the parameters of interest are presented. These results are well within the Atomic Energy Commission's Interim Acceptance Criteria. 4 references. (auth)